IR 05000423/1985017

Meeting Rept 50-423/85-17 on 850325 Re Use of Simulator for Upcoming Operator Exams During May 1985.Simulator Deemed Adequate for Use During Exam.Deficiencies Noted

ML20127J965
Person / Time
Site:	Millstone
Issue date:	06/05/1985
From:	Dante Johnson, Keller R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20127J932	List: IR 05000423/1985017 ML20127J931
References
50-423-85-17-MM, NUDOCS 8506270203
Download: ML20127J965 (4)

Text

"

.

- - .

s'

s

'

U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Meeting Report No. 85-17 Docket N Licensee: Northeast Nuclear Energy Company Facility: Millstone Unit 3 Meeting At: King of Prussia, Pennsylvania Date: March 25, 1985 Prepared By:

D. F. 6'ohnson, Le Reactor Engineer (Examiner)

6/r[B[

' 'date Approved By:  ! [ N R. M. Keller, Chief, Reactor Projects Section date IC Meeting Summary:

' Meeting was held to discuss the use of the Millstone 3 simulator for upcoming NRC operator licensing examinations during May 1985. It directly followed the meeting regarding the upgraded requalification program at Haddam Nec PDR G ADOCK 05000423 PDR Enclosure 1

-,

,

- ~ .

l DETAILS Licensee Attendees C. F. Sears, Vice President R. Z. Test, Director of Nuclear Training NRC Attendees W. Kane, Deputy Director, Division of Reactor Projects H. Kister, Chief, Projects Branch No. 1 E. Wenzinger, Chief, Reactor Projects Branch No'. 3 E. McCabe, Chief, Reactor Projects Section 3B R. Keller, Chief, Reactor Projects Section 1C D. Johnson, Lead Reactor Engineer (Examiner)

D. Ruscitto, Reactor Engineer (Examiner)

D. Coe, Reactor Engineer (Examiner) Licensee Presentation and Discussion Licensee reiterated their concerns outlined in their letter to the Region I Regional Administrator dated February 28, 1985 regarding the use of the Millstone 3 simulator for upcoming NRC operator license examination . NRC Action During the meeting, NRC Region I license examiners committed to inspect and exercise the Millstone 3 training simulator and to determine its suit-ability for use during the operator license examination in May 1985. T time period scheduled for their evaluation was April 9-11, 198 The results of the evaluation are contained in Enclosure ,

Enclosure 1

.

. ..

C Docket N Subject: NRC Evaluation of Millstone 3 Simulator for License Examinations On April 9 through April 11, 1985, three NRC and two contract license examiners evaluated the readiness of the Millstone 3 simulator for conducting operator licensing exams during the two weeks beginning May 13, 1985. In addition, plant tours were conducted to familiarize the examiners with the plant and to evaluate the general degree of plant completion and readiness for administering oral exams. The following NRC examiners were present:

NRC D. F. Johnson, Lead Reactor Engineer (Chief Examiner)

D. G. Ruscitto, Reactor Engineer (Examiner)

D. H. Coe, Reactor Engineer (Examiner)

The following contract examiners (EG&G) were also present:

EG&G R. Sailor P. Isaksen An exit meeting was held on April 12, 1985 with Johnson and Coe representing the NRC and the following Northeast Nuclear Energy Company representatives:

NNEC J. M. Black, Nuclear Project Manager, Training R. H. Haynes, Simulator Technical Systems Manager B. Landon, Simulator Program Supervisor The results of this evaluation are that the Millstone 3 simulator is adequate for use during the May 1985 exa However, the following deficiencies or questions were noted:

Simulator Radiation monitor alarms were inoperable during malfunction CR01 (Fuel Element Failure). In a letter from W. J. Landon of NNEC to D. F. Johnson of NRC Region I dated April 30, 1985, NNEC indicated that the alarm setpoints have been adjusted. Verification of proper simulator response will be made during the May 1985 license examination Enclosure 2

.

. ,

,l 2 FCV 121 fails "as is" instead of full open or shut as indicated in the simulator malfunctions book. NNEC has altered the actual malfunction to conform to existing documentation, as reported in the above April 30 lette . No surveillance procedure is available for the emergency diesel genera-tors. NRC will use Tech Specs to walk through surveillance requirement . SI reset lockout appears to last an inordinate amount of time (approxi-mately 20 minutes). NNEC will evaluate and inform NRC if simulator response is correc plant Lighting around Auxiliary Shutdown Boards (ASB), is inadequate. NNEC will provide additional lighting or flashlights for candidate / examiner us . Local procedures were not available at the ASB's or emergency diesel NNEC will either provide local procedures or copies available in control room for examination.us . Portable Radiation Monitoring equipment not available in the plant. NNEC will ensure such equipment is available for exam us In summary, this visit proved valuable in assessing plant and simulator readi-ness for upcoming operator license exams and in identifying deficiencies which, when corrected, will enhance the overall examination process at Millstone The courtesy and cooperation of the Millstone 3 training staff is noted with appreciatio s Enclosure 2