ML20132C929

Insp Rept 70-1113/85-15 on 850812-16 & 23.No Violations or Deviations Identified.Major Areas Inspected:Mgt Organization & Controls,Training,Nuclear Criticality Safety,Audits, Operations & Fuel Storage

ML20132C929
Person / Time
Site:	07001113
Issue date:	09/04/1985
From:	Mcalpine E, Troup G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20132C912	List: ML20132C908 ML20132C929
References
70-1113-85-15, NUDOCS 8509270188
Download: ML20132C929 (7)

Text

-,

53M4 UNITED STATES q'o NUCLEAR REGULATORY COMMISSION

[ , REGION 18 g j 101 MARIETTA STREET.N.W.

• _;* ATLANTA. GEORGI A 30323 SEP 131985 Report No.: 70-1113/85-15 Licensee: General Electric Company Wilmington, NC 28401 Docket No.: 70-1113 License No.: SNM-1097 Facility Name: General Electric Company Inspection Conducted: p gust p 6 and August 23, 1985 Inspector:

G. L. Troup- '

,M

~/

7f!C[

Date/ Signed Accompanying Personnel: J. N. Grace-(August 14,1985)

K. P. Barr (August 14,1985)

Approved by: "(lk E. J. McA1)ine, Chief,) Material Control and

~

9/Yh$

Date Signed Accountability Section, Nuclear Materials Safety and Safeguards. Branch, Division.of Radiation Safety and Safeguards

SUMMARY

Scope: This routine,. unannounced inspection entailed 33 inspector-hours on site in the areas of management organization and controls, training, nuclear criticality safety, audits, operations, and fuel storage. Additionally, a management meeting was held on August 14, 1985 Results: Of the areas inspected, no violations or deviations were identified.

8509270188 850913 PDR ADOCK 07001113 C PDR 1

J 3

REPORT DETAILS

1. Persons Contacted Licensee Employees E. A. Lees, General Manager

• W. W. McMahon,. Manager,. Quality Assurance

• J. E. Bergman, Manager, Manufacturing

• R. A. Petelinkar, Manager, Site Operations and Materials Systems

• B. F. Bentley, Manager, Fuel Chemical Operations

• G. R. Pearson, Manager, Uranium Fuel Fabrication

• C. M. Vaughan, Manager, Regulatory Compliance

• W. C. Peters, Manager, Nuclear Safety Engineering

• R. E._ Lennon, Senior Manager, Manufacturing Training and Program Development

• W. B. Smalley, Manager, Environmental Protection F. C. Eschenlauer, Supervisor, Metallurgical Laboratory J. T. Taylor, Senior Nuclear Safety Engineer G. M. Bowman, Senior Nuclear Safety Engineer S. P. Murray, Senior Nuclear Safety Engineer R. H. (). Folleck, Senior Specialist - License Engineeri~ng G. R. Mallett, Senior Engineer - Measurements and Statistics B. S. Dunn, Specialist - Licensing Support W. B. Haverty, Analyst - Nuclear Material Control R. J. Keenan, Nuclear Safety Engineer

• T. R. Crawford, Environmental Protection Engineer Other licensee employees contacted . included technicians, operators, and office personnel.

• Attended exit interview

2. Exit Interview The inspection scope and findings were summarized on August 16, 1985, with those persons-indicated in paragraph I above. The inspector described the areas inspected and discussed in detail the inspection findings listed

~

below. No dissenting comments were received from the licensee. The~

licensee stated that design, process and operational information associated with the Uranium Process Management Project (UPMP) would be considered company proprietary under the terms of 10 CFR 2.790.

3. Licensee Action on Previous Enforcement Matters Not inspected.

L i

2

4. Management Organization'and Controls'(88005)

a. Organizational Structures The responsibilities of the licensee's key positions with safety related responsibilities and qualifications of the personnel filling the positions were reviewed in report 70-1113/85-07. 'The inspector discussed the assignments with licensee representatives and determined that there had been no changes or reassignments since the last review.

b. Safety Review Committee (1) Section 2.3.1 of the license application states ~ that the Safety-Review Committee (SRC) shall be comprised of at least five members appointed by' the Department General Manager, shall meet at least four times a calendar year and shall be responsible for performing certain specified reviews. P/P 40-1, "Wilmington Safety Review Committee" appoints the members- of the position as well. as designates the Chairman and secretary. The procedure was approved by the Department General Manager.

(2) The inspector reviewed the minutes of the meetings- held on June 19, August 28 and December 7,1984, and meetings held on March 28, April 18, April 19 and April 24, 1985. The minutes indicated that a- quorum was present for each meeting, and that >

items requiring action by managers were identified and responsi-bility assigned. The 1985 meetings constituted a review of the status and open work on the UPMP project (See paragraph 9).

No violations or deviations were identified.

5. Training / Retraining (88010)

a. Section 2.6 of the license application requires that nuclear safety training be performed by instructors cert.ified by the manager of the criticality safety and radiation safety functions. This requirement is implemented by P/P 40-17, " Nuclear Safety Training", which requires the documentation of the qualification of instructors and approval by the Manager, Nuclear Safety Engineering. The inspector verified that qualification records .had been prepared and approved for persons currently conducting training.

b .- Section 2.6 of the licensee application ' requires employees will be retrained every two years. - The inspector discussed this requirements with licensee representatives and reviewed computer records used to track the status . of retraining, and identify individuals requiring retraining. During tours of the process ' areas, discussions with ir.dividuals indicated that they had received nuclear safety training within the past year and that they were aware.of the requirements for periodic retraining.

3

6. Nuclear Criticality Safety (88015)

a. Facility Modification and Changes The inspector reviewed four facilities change requests . and the 1

associated ' nuclear safety analyses. The inspector verified that the analyses were conducted using approved evaluation methods and that the analyses were verified by an inde' pendent-reviewer. The inspector also verified that preoperational audits had ~ been conducted prior to the issuance of the final approval by Nuclear Safety Engineering,:and that a Nuclear Safety Release / Requirement (NSR/R) had been approved by the Area Manager and Nuclear Safety Engineering prior to f ssuance. The inspector also reviewed six change requests which were '

ev'aluated as not

-requiring a nuclear. safety analysis. \'

No violations or deviations were identified.,. ,

b. Nuclear Safety Analysis Methods The inspector discussed the methods used to perform nuclear safety calculations with the cegnizant individuals and verified that the methods used were in= accordance with the licensee requirements.

Calculational methods which may be used and individuals designated as qualified to perform analyses and/or to perform the independent verification are specified in NSI E-4.0, " Criticality Safety Analysis Methods and Verification". A licensee representative informed the inspector that three approved codes are presently used.

No violations or deviations were identified.

c. SNM Containers Table 13.7 of the license application lists the shipping containers authorized for use by the licensee. A licensee representative informed the inspector that no other containers were in use. During tours of-the facility the inspector did not observe any shipping containers which were not listed in Table 13.7.

d. Proceduces _

The inspector reviewed five procedures for performing nuclear safety

' analyses. No changes or revisions to these procedures had been made

.since the last review.

", , 7. Audits (88005,88015)

a. Sections 2.8.1 and 2.8.3 of the license appl'fcation specify require-ments for internal quarterly audits and. biennial external audits. The inspector reviewed the written report for'the second quarter internal audit conducted in June 1985 and an external' audit conducted by the Quality Assurance and Reliability Operation (QAR0) in May 1985. The y -j

4 inspector verified that the audit findings were documented and submitted to management, that corrective actions were documented, and each item closed after the adequacy was determined.

b. The inspector reviewed .the_ audit reports and determined that auditors were rotated during the quarterly audits. A memorandum from the Manager, Nuclear Safety Engineering Edated September- 17, 1984, designated the senior members of the criticality safety and radiation safety functions for auditor qualification. Individuals to perform audits are designated in writing prior to the audit.

c. Nuclear Safety Instruction NSI 2.0, " Internal Nuclear Safety Audits",

requires that quarterly audits be conducted at the Greenville, SC warehouse. An audit form has been p epared for these audits. The inspector reviewed fthe audit reports for the audits _ conducted on February 21, 1985 a6d - May 23, 1985. Additionally, the inspector

~

observed.the audit conducted on August 23, 1985 (see paragraph 11).

No violations or deviations'were identified.

8. Operations Review (88020, 88025)

a. Tours During the inspection, tours were made of various work areas to observe operations. Items. reviewed or verified included:

-(1) Special nuclear material was stored in arrays on carts, conveyors, and process areas, and in designated storage locations in accordance with license requirements.

(2) Housekeeping and industrial safety provisions :in all areas were acceptable.

(3) Operating ~ procedures (PRODS) were available in the various areas.

Nuclear Safety Release / Requirements and Radiological Safety Instructions were also available.

(4) Compressed gas cylinders were constrained by a rope or chain in accordance with good industrial safety' practices.

(5) Containers of SNM were marked to identify the enrichment of the material. Observed enrichments were within posted limits.

(6) Quantities ofc SNM in waste boxes were checked for conformance of labeled quantities'in each box and the total in the array with the posted limits for the area. ,

5

b. Hydrofluoric Acid Shipments

! Section 1.8.3.1 of the License Application (a condition of the license) authorizes the sale of hydrofluoric acid to a non-licensed company provided that the uranium concentration is less than 3 ppm. The inspector reviewed the records for the shipments of acid made in 1985 and determined that the material was less than the uranium concentra-tion limit and was shipped to the designated receiver.

No violations or deviations were identified.

9. Uranium Process, Management Project (UPMP) (88015, 88020)

I

a. Amendment 3 to' license SNM-1097, dated Febraury 26, 1985, authorized  :

i the use of UPMP to process licensed materials. The licensee has started using several subsystems of UPMP to process uranium bearing process streams.

b. The inspector reviewed the following documents related,to the startup of the UPMP subsystems:

(1) Memoranda dated May 9,1985, May 16,1985, and June 3, 1985, from the Manager, Nuclear Safety Engineering to the Manager, Fuel Chemical Operations which approved the operation of the systems with uranium and constituted the official nuclear safety releases.

(2) Safety Review Committee minutes for meetings 3.on March 28, April 18, April 19, and April 24, 1985, which pertained Eto t.he status, training, and preoperational testing for. UPMP. .

(3) Approximately 25 Nuclear Safety Release /Requireme'nts (NSR/Rs) for proper review and approval and verification thdt nuclear safety "

requirements were consistent with the license ' application and nuclear safety analyses. A total of 63 NSR/Rs have been prepared and approved.

No violations or deviations were identified.

10. Management Meeting 3

a. On Augu'st 14, 1985, a management meeting was held at the Nuclear Fuel Manufacturing Department.

NRC Attendees ,

J. Nelson Grace, Regional Administrator, Region II i;

K. P. Barr, Chief, Nuclear Materials Safety and Safeguards Branch G. L. Troup, Fuel, Facilities Inspector a

.f

?

~- -.

-._g,,. ,7,. gv ,_ ~ . . - _ . _ . . - ,, - - . _.. . -

6 GE - NFMD attendees E. A. Lees, General Manager J. E. Bergman, Manager, Manufacturing R. A. Petelinkar, Manager, Site Operations and Materials Systems

, W. W. McMahon, Manager, Quality Assurance J. L. Harmon, Manager, Manufacturing Technology and Engineering Operations B. F. Bentley, Manager, Fuel Chemical Operations C. M. Vaughan, Manager, Regulatory Compliance W. C. Peters, Manager, Nuclear Safety Engineering S. P. Murray, Senior Nuclear Safety Engineer

b. The purpose of the meeting was to familiarize the Regional Adminis'-

trator with the facilities and operations of the NFMD. Topics discussed included the organization, qualifications of key managers, site facilities, and fuel manufacturing operations. The meeting

. included a tour of the fuel manufacturing areas and associated support facilities.

11. Greenville Fuel Storage Facility

a. Sections 1.8.4.2 and 1.8.4.3 of the license application authorize the licensee to store uranium and completed fuel assemblies at the storage-warehouse in Greenville, SC. Fuel assemblies may be stored either in packages as for transport in a Fissile Class I package or in the metal inner containers of the RA-series shipping package under certificate of compliance USA /986/AF.

b.- On August 23, 1985, the inspector toured the . warehouse to observe operations. Items reviewed or verified included:

(1) Nuclear Safety requirements (NSR/Rs) were current, and were posted in each section of the warehouse.

(2) Materials were contained in approved shipping containers,-and were-stored iri approved arrays.

(3) All licensed material was stored inside of the ware. house.

(4) Flammable and combustible materials were stored in a designated steel storage cabinet.

(5) Warehouse doors were posted with ' appropriate radiation warning I signs.

'(6) Security and fire alarms were installed and functional. l No violations or deviations were identified.

l l

l

_