ML022070344
| ML022070344 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/25/2002 |
| From: | Ernstes M Operator Licensing and Human Performance Branch |
| To: | Christian D Virginia Electric & Power Co (VEPCO) |
| References | |
| 50-338/2002-301, 50-339/2002-301 | |
| Download: ML022070344 (12) | |
See also: IR 05000338/2002301
Text
July 25, 2002
Virginia Electric and Power Company
ATTN:
Mr. David A. Christian
Senior Vice President and
Chief Nuclear Officer
Innsbrook Technical Center
5000 Dominion Boulevard
Glen Allen, VA 23060
SUBJECT:
NORTH ANNA POWER STATION - NRC EXAMINATION REPORT
NOS. 50-338/2002-301 AND 50-339/2002-301
Dear Mr. Christian:
During the period June 10-14 and June 24-25, 2002, the Nuclear Regulatory Commission
(NRC) administered operating examinations to employees of your company who had applied for
licenses to operate the North Anna Power Station. At the conclusion of the examination, the
examiners discussed the examination questions and preliminary findings with those members
of your staff identified in the enclosed report. The written examination was administered by
your staff on June 6, 2002.
Eleven of the thirteen applicants passed both the written and operating examinations. One
Reactor Operator applicant and one Senior Reactor Operator applicant failed the written
examination. A Simulation Facility Report is included in this report as Enclosure 2. There were
three Post Examination comments. Post examination comment resolution is included in this
report as Enclosure 3.
In accordance with 10 CFR 2.790 of the NRCs Rules of Practice, a copy of this letter and its
enclosures 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).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/NRC/ADAMS/index.html
(the Public Electronic Reading Room).
Sincerely,
/RA/
Michael E. Ernstes, Chief
Operator Licensing and
Human Performance Branch
Division of Reactor Safety
Docket Nos.: 50-338, 50-339
Enclosures: (See page 2)
2
VEPC
Enclosures:
1. Report Details
2. Simulation Facility Report
3. NRCs Resolution to the Facilitys Post Examination Comments
cc w/encls:
Stephen P. Sarver, Director
Nuclear Licensing and
Operations Support
Virginia Electric and Power Company
Electronic Mail Distribution
D. A. Heacock
Site Vice President
North Anna Power Station
Electronic Mail Distribution
Executive Vice President
Old Dominion Electric Cooperative
Electronic Mail Distribution
County Administrator
Louisa County
P. O. Box 160
Louisa, VA 23093
Lillian M. Cuoco, Esq.
Senior Nuclear Counsel
Dominion Nuclear Connecticut, Inc.
Electronic Mail Distribution
Attorney General
Supreme Court Building
900 East Main Street
Richmond, VA 23219
H. Ashley Royal
Manager Nuclear Training
North Anna Power Station
P. O. Box 402
Mineral, VA 23117
3
VEPC
Distribution w/encls:
S. Monarque, NRR
RIDSNRRIPMLIPB
PUBLIC
OFFICE
RII:DRS
RII:DRS
RII:DRS
RII:DRS
RII:DRP
RIII
SIGNATURE
/RA/
/RA By GHopper for/
/RA/
/RA By GHopper for/
/RA By LGarner for/
NAME
RAiello:pmd
LMiller
BMonk
MErnstes
KLandis
MMorris
DATE
7/22/2002
7/23/2002
7/23/2002
7/ /2002
7/25/2002
7/25/2002
E-MAIL COPY?
YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO
PUBLIC DOCUMENT
YES
NO
OFFICIAL RECORD COPY DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML022070344.WPD
Enclosure 1
NUCLEAR REGULATORY COMMISSION
REGION II
Docket Nos.:
50-338, 50-339
License Nos.:
Report Nos.:
50-338/02-301, 50-339/02-301
Licensee:
Virginia Electric and Power Company (VEPCO)
Facility:
North Anna Power Station
Location:
1024 Haley Drive
Mineral, VA 23117
Dates:
Operating Tests - June 10-14 and June 24-25, 2002
Written Examination - June 6 , 2002
Examiners:
R. Aiello, Chief Examiner
L. Miller, Senior Operations Engineer
R. Monk, Operations Engineer
R. Morris, Operations Engineer
Approved by:
M. Ernstes, Chief
Operator Licensing and Human Performance Branch
Division of Reactor Safety
SUMMARY OF FINDINGS
ER 05000338-02-301, IR 05000339-02-301 on 6/10-14/2002 and 6/24-25/2002, Virginia
Electric and Power Company, North Anna Power Station licensed operator examinations.
The NRC examiners conducted an announced operator licensing initial examination in
accordance with the guidance of Examiner Standards, NUREG-1021, Revision 8, Supplement
1. This examination implemented the operator licensing requirements of 10 CFR §55.41,
§55.43, and §55.45. No significant issues were identified.
Six Reactor Operator (RO) applicants and seven Senior Reactor Operator (SRO) applicants
received written examinations and operating tests. The NRC administered the operating tests
during the period June 10-14 and June 24-25, 2002. The licensee administered the written
examination on June 6, 2002. Eleven of the thirteen applicants passed both the written and
operating examinations. One Reactor Operator applicant and one Senior Reactor Operator
applicant failed the written examination.
Report Details
4.
OTHER ACTIVITIES (OA)
4OA5 Operator Licensing Initial Examinations
a.
Inspection Scope
The NRC conducted a regular, announced operator licensing initial examination during
the period June 10-14 and June 24 -25, 2002. Six RO applicants and seven SRO
applicants received written and operating examinations. The examiners reviewed the
examination security measures to ensure examination security and integrity.
b.
Issues and Findings
No findings of significance were identified.
The NRC developed the operating test outline. The licensee developed the operating
test from the submitted outline. The NRC developed the written examination. Both
exams were created in accordance with NUREG 1021, Revision 8, Supplement 1. The
NRC administered the approved operating tests during the period of June 10-14 and
June 24-25, 2002. The licensee staff administered the approved written examination
on June 6, 2002.
Eleven of the thirteen applicants passed both the written and operating examinations.
One Reactor Operator applicant and one Senior Reactor Operator applicant failed the
written examination. Details of each applicants deficiencies are described in the
individuals examination report, Form ES-303-1, Operator Licensing Examination
Report. Copies of the evaluations have been forwarded under separate cover to the
Training Manager to enable the licensee to evaluate these deficiencies and provide
appropriate remedial training for those operators as necessary.
The NRC submitted the written examinations (ADAMS Accession Number
ML022050114). Post examination comments were submitted by the licensee (ADAMS
Accession Number ML022050197). The NRCs resolution to these comments is
included as Enclosure 3.
4OA6 Meetings
Exit Meeting Summary
The Chief Examiner presented the preliminary examination results on June 25, 2002, to
members of licensee management. The licensee acknowledged the examination results
presented.
The inspectors asked the licensee whether any materials examined during the
inspection should be considered proprietary. No proprietary information was identified.
2
PARTIAL LIST OF PERSONS CONTACTED
Licensee
S. Crawford, Instructor
A. Royal, Training Manager
J. Scott, Supervisor, Operations Training
D. Tiblis, Instructor
NRC
R. Aiello, Chief Examiner
L. Miller, Senior Operations Engineer
R. Monk, Operations Engineer
M. Morris, Region III Operations Engineer
Enclosure 2
SIMULATION FACILITY REPORT
Facility Licensee: North Anna
Facility Docket Nos.: 50-338, 50-339
Operating Tests Administered on: June 10-14 and June 24-25, 2002
This form is to be used only to report observations. These observations do not constitute audit
or inspection findings and are not, without further verification and review, indicative of
noncompliance with 10 CFR 55.45(b). 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.
No simulator configuration or fidelity items were identified.
Enclosure 3
NRCs RESOLUTION TO THE FACILITYS POST EXAMINATION COMMENTS
Facility comment to SRO Question #72 accepted: Typographical error. The correct answer
should be A (97%)
Facility comment to SRO Question #89 accepted: Typographical error. The correct answer
should be C (To prevent damage to the pressurizer heaters)
Facility comment to RO/SRO Question #15 NOT accepted: In accordance with NCRODP-74-
NA, the steam undergoes an extremely rapid expansion which is almost isenthalpic (BTUs of
energy per pound mass remain constant). The expansion causes the BTUs to be contained in
a much larger volume. Temperatures will indicate between 200 and 300 degrees F. Based on
the initial conditions, RCS temperature and pressure will decrease and stabilize out long after
the reactor trip and after the PRT rupture disc breaks. Since enthalpy is basically constant
across the safety valve, tail piece temperatures will increase to around 200 and 300 degrees F,
then continue to increase slowly until the PRT rupture disc breaks. The tail pipe temperatures
will start to decrease proportionately with the drop in RCS pressure and temperature.
Based on the facilitys post exam comment: The NRC requested the facility to set up and run a
test on the simulator in order that a graph of tail piece temperature vs time could be created for
reference. This graph is included as Attachment 1 to this enclosure. Based on the time
increments, answer D is the only correct answer for the following reasons:
1.
Each time increment on the trace appears to be ~ 40 seconds. This results in the
following rates of temperature increase:
a.
Temp increase from temp of ~100 degrees to ~ 265 degrees occurs over ~1st
40 seconds for a rate of ~248 degrees/minute. Note that 100 degrees appears
to be temp just prior to safety opening.
b.
Temp increase from 265 to ~peak temp of ~275 occurs over ~50 seconds for a
rate of ~12 degrees/min.
c.
Temp decrease from ~275 to ~175 occurs over ~ 70 seconds for a rate of ~85
degrees/minute.
Therefore, given these rates of temp increase and decrease, the NRC believes that it is not
reasonable to credit answer C as correct. The second part of distractor C, (...and then
slowly decrease) would not appear to reasonably describe the rate of temp decrease after the
PRT rupture disc breaks. Answer D is valid based on the first two temp increase rates
described above - "increase to between 200 and 300 and then slowly increase."
Enclosure 3