IR 05000318/2004301

IR Calvert Cliffs, Units 1 & 2, Operator and Senior Reactor Operator Initial Examination Report No. 05/000317/2004301 and 05000318/2004301

ML041070079
Person / Time
Site:	Calvert Cliffs
Issue date:	04/15/2004
From:	Conte R NRC/RGN-I/DRS/OSB
To:	Vanderheyden G Constellation Generation Group
Conte R
References
050-317/04-301, 050-318/04-301
Download: ML041070079 (12)

Text

ril 15, 2004

SUBJECT:

CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2, OPERATOR AND SENIOR REACTOR OPERATOR INITIAL EXAMINATION REPORT NO.

05000317/2004301 AND 05000318/2004301

Dear Mr. Vanderheyden:

This report transmits the results of the Reactor operator (RO) and Senior reactor operator (SRO) licensing examination conducted by the NRC during the period of February 27 - March 4, 2004. 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 9).

Based on the results of the examination, all five Senior Reactor Operator and all four of the Reactor Operator applicants passed all portions of the examination. The nine applicants included four ROs, two instant SROs and three upgrade SRO. Examination results indicated that the applicants were well prepared for the examination. Mr. DAntonio discussed performance insights observed during the examination with training and operations management on March 4, 2004. On March 24, 2004, final examination results, including individual license numbers, were given during a telephone call between Mr. DAntonio and Mr. Kent Mills.

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; RO and SRO Written - Accession Number ML040970260; RO and SRO Operating Section A -

Accession Number ML040970557; RO and SRO Operating Section B - Accession Number ML040970584; and RO and SRO Operating Section C - Accession Number ML040970590 and facility Post Examination Comments on the Written Exams - Accession No. ML040970592.

ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Mr. George Vanderheyden 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 Nos. 050000317/05000318 License Nos. DPR-53/DPR-69

Enclosure:

Initial Examination Report No. 05000317/2004301 and 05000318/2004301

REGION I==

Docket Nos: 05000317/05000318 License No: DPR-53/DPR-69 Report No: 05000317/2004301 and 05000318/2004301 Licensee: Constellation Energy Group Facility: Calvert Cliffs Units 1 & 2 Dates: February 27, 2004 (Written Examination Administration)

March 1-4, 2004 (Operating Test Administration)

March 5, 2004 (Facility Grading Complete)

March 15-19, 2004 (Examination Grading)

Examiners: Joseph DAntonio, Operations Engineer (Chief Examiner)

Steve Barr, Operations Engineer (under instruction)

Julian Williams, Senior Operations Engineer Richard J. Conte, Chief, Operational Safety Branch (auditor)

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

SUMMARY OF FINDINGS IR 05000317&318/2004-301; February 27 - March 4, 2004; Calvert Cliffs Nuclear Power Plant, Units 1 and 2; Initial Operator Licensing Examination. Nine of nine applicants passed the examination (four reactor operators, two SRO instants, and three SRO upgrades).

The written examinations were administered by the facility and the operating tests were administered by three NRC region-based examiners. There were no inspection findings of significance associated with the examinations.

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 examination team developed the written and operating initial examination and together with Calvert Cliffs Nuclear Power Plant, Units 1 and 2 training and operations personnel verified or ensured, as applicable, the following:

• The examination was prepared and developed in accordance with the guidelines of Revision 9 of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors. A review was conducted both in the Region I office and at the Calvert Cliffs Nuclear Power Plant, Units 1 and 2 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 examiners administered the operating portion of the examination to all applicants from March 1-4, 2004. The written examination was previously administered by the Calvert Cliffs Nuclear Power Plant training staff on February 27, 2004.

b. Findings Grading and Results All nine applicants (five SROs and four ROs) passed all portions of the initial licensing examination.

The facility had three post exam comments which were resolved as discussed in attachment 2.

Examination Administration and Performance Two simulator issues were identified and are detailed in the enclosed Simulation Facility Report, attachment 1.

4OA6 Exit Meeting Summary On March 24, 2004, the NRC provided conclusions and examination results to Calvert Cliffs Nuclear Power Plant, Units 1 and 2 management representatives via telephone.

License numbers for all nine applicants were also provided during this time.

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.

KEY POINTS OF CONTACT LICENSEE Julie Sickle, Manager, Nuclear Training Kent Mills, General Supervisor, Nuclear Plant Operations Brian Hayden Supervisor Initial License Training Nick Lavato Supervisor, Requal Training Mike Wassem Instructor/ written exam developer NRC Joseph DAntonio Operations Engineer Steve Barr Operations Engineer Richard Conte Chief, Operational Safety Branch LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED ITEM NUMBER TYPE DESCRIPTION NONE

Attachment 1 ES501 Simulation Facility Report Facility Licensee: Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Facility Docket Nos: 50-317/318 Operating Tests Administered on: March 1-4, 2004 This form is to be used only to report observations. These observations do not constitute audit or inspection findings and, without further verification and review, are not indicative of noncompliance with 10 CFR 55.46. These observations do not affect NRC certification or approval of the simulation facility other than to provide information that may be used in future evaluations. No licensee action is required in response to these observations.

While conducting the simulator portion of the operating test, examiners observed the following items:

ITEM DESCRIPTION Simulator Lockup During the administration of one scenario, the simulator ceased responding. This required reboot of the machine, and the scenario could not be either restarted or backtracked. An extra scenario was run to complete the exam.

Diesel Generator During the administration of a JPM requiring 2A 4KV bus to be Output Breaker Trip transferred from 2A diesel to offsite power, for two applicants the diesel output breaker tripped when the offsite normal feeder breaker was closed.

The examiners observed no errors by the applicants which could have caused these trips.

A2-2 Attachment 2 NRC Resolution of Facility Comments (ML040970592)

Question # 5 The question asks about plant response to an RCP trip.

Summary of Facility Comment and Recommendation:

There is no correct answer provided, delete the question.

NRC Resolution:

Question deleted. The originally specified correct answer would be correct if there were no flow in the loop in which the RCP tripped, however in this CE plant there is still one RCP running in the affected SG loop. None of the distractors correctly describe what the plant response would be.

Question # 35 This question asks about plant response to a controller failure in the pressurizer pressure control system.

Summary of Facility Comment and Recommendation:

There is no correct answer provided, delete the question NRC Resolution:

Question deleted. The originally specified correct answer is based on the failure of a different controller than the one specified in the question. The response to a failure of the controller in the question would be closure of the spray valves, which was not one of the available answers.

Question # 68 This question asks about the required means of informing management of an RCS leakrate increase.

Summary of Facility Comment and Recommendation:

The wrong answer was specified in the key. The actual leakrate calculated from the conditions in the question makes "A" rather than "D" the correct answer.

NRC Resolution:

A2-2 Question deleted. The facility reference has the operator evaluate both RCS leakrate and containment sump pumping frequency to categorize leakage, with no clarification as to whether these are "or" conditions or "and" conditions. If "or", then all the categories apply. If "and", then only one category ever applies. The correct answer could not be determined.