ML022750615

Exam Report 2002-301 Dtd 10/2/02

ML022750615
Person / Time
Site:	Millstone
Issue date:	10/02/2002
From:	Conte R Division of Nuclear Materials Safety I
To:	Price J, Danni Smith Nuclear Technology Services
Shared Package
ML020580355	List: ML022750615
References
50-423/02301 IR-02-301
Download: ML022750615 (9)

Text

October 2, 2002 Mr. J. Alan Price, Vice President -

Nuclear Technical Services/Millstone c/o Mr. D. A. Smith, Manager -

Regulatory Affairs Dominion Nuclear Connecticut, Inc.

Rope Ferry Road Waterford, CT 06385

SUBJECT:

MILLSTONE 3 SENIOR REACTOR OPERATOR INITIAL EXAMINATION REPORT NO. 50-423/02-301

Dear Mr. Price:

This report transmits the results of the senior reactor operator (SRO) licensing examination conducted by the NRC during the period of Aug 12-15, 2002. This examination addressed areas important to public health and safety and was developed and administered using the guidelines of the Examination Standards for Power Reactors (NUREG-1021, Revision 8, Supplement 1).

Based on the results of the examination, all five Senior Reactor Operator applicants passed all portions of the examination. Examination results indicated that the applicants were well prepared for the examination.

Mr. DAntonio discussed performance insights observed during the examination with Mr. Dale Brodsky on August 15, 2002. On August 26, 2002, final examination results, including individual license numbers, were given during a telephone call between Mr. Brodsky and Mr.

DAntonio.

In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). These records include the final examination and are available in ADAMS ( SRO Written - Accession Number ML022550590; SRO Operating Section A - Accession Number ML022550625; SRO Operating Section B - Accession Number ML022550612; and SRO Operating Section C - Accession Number ML022550644). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/ADAMS.html (the Public Electronic Reading Room).

Mr. J. Alan Price 2 Should you have any questions regarding this examination, please contact me at (610) 337-5183, or by E-mail at RJC@NRC.GOV.

Sincerely,

/RA/

Richard J. Conte, Chief Operational Safety Branch Division of Reactor Safety Docket No. 50-423 License No. NPF-49

Enclosure:

Initial Examination Report No. 50-423/02-301 cc w/encl:

D. A. Christian, Senior Vice President - Nuclear Operations and Chief Nuclear Officer W. R. Matthews, Vice President and Senior Nuclear Executive - Millstone S. E. Scace, Director, Nuclear Engineering G. D. Hicks, Director, Nuclear Station Safety and Licensing C. J. Schwarz, Director, Nuclear Station Operations and Maintenance P. J. Parulis, Manager, Nuclear Oversight D. A. Smith, Manager, Licensing L. M. Cuoco, Senior Nuclear Counsel N. Burton, Esquire V. Juliano, Waterford Library S. Comley, We The People J. Buckingham, Department of Public Utility Control E. Wilds, Director, State of Connecticut SLO Designee First Selectmen, Town of Waterford D. Katz, Citizens Awareness Network (CAN)

R. Bassilakis, CAN J. M. Block, Attorney, CAN J. Besade, Fish Unlimited G. Winslow, Citizens Regulatory Commission (CRC)

J. Markowicz, Co-Chair, NEAC E. Woollacott, Co-Chair, NEAC R. Shadis, New England Coalition Staff W. Meinert, Massachusetts Municipal Wholesale Electric Company

Mr. J. Alan Price 3 Distribution w/encl: (VIA E-MAIL)

Region I Docket Room (with concurrences)

A. Cerne, SRI - NRC Resident Inspector H. Miller, ORA J. Wiggins, ORA S. Richards, NRR (ridsnrrdipmlpdi)

T. Madden, OCA H. Nieh, OEDO R. Ennis, PM, NRR G. Wunder, Backup PM, NRR V. Nerses, PM, NRR B. McDermott, RI K. Jenison, RI D. Screnci, PAO W. Lanning, DRS R. Crlenjak, DRS R. Conte, DRS J. DAntonio, Chief Examiner, DRS C. Buracker, DRS (Master Exam File)

DRS File DOCUMENT NAME:C:\ORPCheckout\FileNET\ML022750615.wpd ADAMS PACKAGE: ML020580355 After declaring this document An Official Agency Record it will be released to the Public.

To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy OFFICE RI/DRS RI/DRS RI/DRS RI/DRP NAME CBuracker JDAntonio RJConte BMcDermott DATE 09/18/02 08/29/02 09/28/02 09/26/02 kmj for OFFICIAL RECORD COPY

U. S. NUCLEAR REGULATORY COMMISSION REGION I Docket No(s): 50-423 License No: NPF-49 Report No: 50-423/02-301 Licensee: Dominion Nuclear Facility: Millstone Unit 3 Dates: August 9, 2002 (Written Examination Administration)

August 12-15, 2002 (Operating Test Administration)

August 18-23, 2002 (Examination Grading)

Examiners: Joseph M. DAntonio, Operations Engineer (Chief Examiner)

Approved by: Richard J. Conte, Chief Operational Safety Branch Division of Reactor Safety

SUMMARY

OF FINDINGS IR 05000423/02-301; Aug 9-15, 2002; Millstone 3; Initial Operator Licensing Examination. Five of five applicants passed the examination (two SRO instants, and three SRO upgrades).

The written examinations were administered by the facility and the operating tests were administered by one NRC region-based examiner. There were no inspection findings of significance. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 3, dated July 2000.

ii

Report Details

1. REACTOR SAFETY Mitigating Systems - Reactor Operator (RO) and Senior Reactor Operator (SRO) Initial License Examination

a. Scope of Review The NRC examiner reviewed the facility developed written and operating initial examinations and together with Millstone 3 training and operations personnel verified or ensured, as applicable, the following:

• The examination was prepared and developed in accordance with the guidelines of Revision 8, Supplement 1 of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors. A review was conducted both in the Region I office and at the Millstone 3 plant and training facility. Final resolution of comments and incorporation of test revisions were conducted during and following the onsite preparation week.

• Simulation facility operation was proper.

• A test item analysis was completed on the written examination for feedback into the systems approach to training program.

• Examination security requirements were met.

The NRC examiner administered the operating portion of the examination to all applicants from August 12-15, 2002. The written examination was previously administered by the Millstone 3 training staff on August 9, 2002.

b. Findings Grading and Results All five SRO applicants passed all portions of the initial licensing examination.

The facility had no post-examination comments.

Examination Administration and Performance One issue was identified concerning interpretation of Technical Specifications (TS). In a scenario involving loss of a reactor coolant pump, the SRO applicants stated they would consider instrumentation in the idled loop operable and would not place the associated reactor trip system bistables in the tripped condition. This was correct in accordance with facility procedures. However, the inspector considered this to be incorrect understanding of TS because loop delta T in the idle loop is no longer a valid reactor power indication and thus the overpower and overtemperature delta T trips from that loop are inoperable. The facility generated CR-02-08417 to document the issue. A subsequent condition report was generated to evaluate the operability of loop

2 temperature instruments for the low-low Tave interlock, P-12, during idle loop operations in hot standby. This was CR-02-10145.

4OA6 Exit Meeting Summary On August 26, 2002, the NRC provided conclusions and examination results to Millstone 3 management representatives via telephone. License numbers for five of six applicants were also provided during this time. License numbers for the remaining applicant was withheld pending completion of the required reactivity manipulations and time on shift in training. Mr.Brodsky was informed that when the NRC is notified, in writing, that these requirements has been completed by this individual, the license would be issued.

The NRC expressed appreciation for the cooperation and assistance that was provided during the preparation and administration of the examination by the licensees training staff.

3 KEY POINTS OF CONTACT LICENSEE Bob Royce Senior Instructor, Operator Training Steve Jackson Senior Instructor, Operator Training Dale Brodsky Supervisor, Initial Operator Training Joe Bergin Acting Manager, Operator Training NRC Joseph DAntonio Operations Engineer LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED ITEM NUMBER TYPE DESCRIPTION NONE