ML032960191
| ML032960191 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 10/23/2003 |
| From: | Fredrickson P Division of Nuclear Materials Safety II |
| To: | Scarola J Carolina Power & Light Co |
| References | |
| IR-03-004 | |
| Download: ML032960191 (18) | |
See also: IR 05000400/2003004
Text
October 23, 2003
Carolina Power and Light Company
ATTN: Mr. James Scarola
Vice President - Harris Plant
Shearon Harris Nuclear Power Plant
P. O. Box 165, Mail Code: Zone 1
New Hill, North Carolina 27562-0165
SUBJECT:
SHEARON HARRIS NUCLEAR POWER PLANT - NRC INTEGRATED
INSPECTION REPORT 050000400/2003004
Dear Mr. Scarola:
On September 27, 2003, the US Nuclear Regulatory Commission (NRC) completed an
inspection at your Shearon Harris reactor facility. The enclosed integrated inspection report
documents the inspection findings, which were discussed on October 6, with you and other
members of your staff.
The inspection examined activities conducted under your license as they relate to safety and
compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed
personnel.
Based on the results of this inspection, no findings of significance were identified.
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) components of NRCs document system
(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-
rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Paul E. Fredrickson, Chief
Reactor Projects Branch 4
Division of Reactor Projects
Docket No.:
50-400
License No.:
Enclosure:
NRC Inspection Report 050000400/2003004
w/Attachment: Supplemental Information
cc w/encl: (See page 2)
2
cc w/encl:
James W. Holt, Manager
Performance Evaluation and
Regulatory Affairs CPB 9
Carolina Power & Light Company
Electronic Mail Distribution
Robert J. Duncan II
Director of Site Operations
Carolina Power & Light Company
Shearon Harris Nuclear Power Plant
Electronic Mail Distribution
Benjamin C. Waldrep
Plant General Manager--Harris Plant
Carolina Power & Light Company
Shearon Harris Nuclear Power Plant
Electronic Mail Distribution
Terry C. Morton, Manager
Support Services
Carolina Power & Light Company
Shearon Harris Nuclear Power Plant
Electronic Mail Distribution
John R. Caves, Supervisor
Licensing/Regulatory Programs
Carolina Power & Light Company
Shearon Harris Nuclear Power Plant
Electronic Mail Distribution
Steven R. Carr
Associate General Counsel - Legal
Department
Progress Energy Service Company, LLC
Electronic Mail Distribution
John H. ONeill, Jr.
Shaw, Pittman, Potts & Trowbridge
2300 N. Street, NW
Washington, DC 20037-1128
Beverly Hall, Acting Director
Division of Radiation Protection
N. C. Department of Environmental
Commerce & Natural Resources
Electronic Mail Distribution
Peggy Force
Assistant Attorney General
State of North Carolina
Electronic Mail Distribution
Public Service Commission
State of South Carolina
P. O. Box 11649
Columbia, SC 29211
Chairman of the North Carolina
Utilities Commission
c/o Sam Watson, Staff Attorney
Electronic Mail Distribution
Robert P. Gruber
Executive Director
Public Staff NCUC
4326 Mail Service Center
Raleigh, NC 27699-4326
Herb Council, Chair
Board of County Commissioners
of Wake County
P. O. Box 550
Raleigh, NC 27602
Tommy Emerson, Chair
Board of County Commissioners
of Chatham County
Electronic Mail Distribution
Distribution w/encl: (See page 3)
3
Distribution w/encl:
C. Patel, NRR
L. Slack, RII EICS
RIDSNRRDIPMLIPB
PUBLIC
OFFICE
DRP/RII
DRP/RII
DRP/RII
SIGNATURE
RXM1
RCH2
GTM
NAME
RMusser:aws
RHagar
GMacdonald
DATE
10/22/2003
10/22/2003
10/22/2003
E-MAIL COPY?
YES
NO YES
NO YES
NO
PUBLIC DOCUMENT
YES
NO
OFFICIAL RECORD COPY DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML032960191.wpd
Enclosure
U. S. NUCLEAR REGULATORY COMMISSION
REGION II
Docket No:
50-400
License No:
Report No:
050000400/2003004
Licensee:
Carolina Power and Light Company
Facility:
Shearon Harris Nuclear Power Plant, Unit 1
Location:
5413 Shearon Harris Road
New Hill, NC 27562
Dates:
June 29, 2003 - September 27, 2003
Inspectors:
R. Musser, Senior Resident Inspector
R. Hagar, Resident Inspector
G. MacDonald, Senior Project Engineer (Sections 1R05, 1R14,
1R15 & 4OA3)
Approved by:
P. Fredrickson, Chief
Reactor Projects Branch 4
Division of Reactor Projects
SUMMARY OF FINDINGS
IR 05000400/2003-004; 06/29/2003 - 09/27/2003; Shearon Harris Nuclear Power Plant, Unit 1;
Routine Integrated Report.
The report covered a three month period of inspection by resident inspectors and a senior
project engineer. 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.
A. Inspector-Identified and Self-Revealing Findings
None.
B. Licensee-Identified Violations
None.
REPORT DETAILS
Summary of Plant Status
The plant operated at or near rated power from the beginning of the inspection period until
August 17, when the reactor was manually tripped following the failure of the A condensate
pump motor. Following replacement of this motor, the plant was returned to power operation on
August 19. On August 27, the A condensate pump motor began to experience an electrical
faulted condition and a rapid downpower was initiated. The plant was stabilized at 45 percent
power and the A condensate pump was secured. The plant was operated at approximately 45
percent power until September 6, when the unit was returned to rated thermal power. The plant
was operated at or near rated power for the remainder of the inspection period.
1.
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity
1R01
Adverse Weather Protection
a.
Inspection Scope
When Hurricane Isabel was predicted for the site on September 18, the inspectors
reviewed actions taken by the licensee in accordance with Procedure AP-300, Adverse
Weather, prior to the onset of that weather, to ensure that the adverse weather
conditions would neither initiate a plant event nor prevent any system, structure, or
component from performing its design function.
b.
Findings
No findings of significance were identified.
1R04
Equipment Alignment
a.
Inspection Scope
Partial System Walkdowns:
The inspectors performed the following three partial system walkdowns, while the
indicated SSCs were out-of-service for maintenance and testing:
B motor-driven auxiliary feedwater train with the A motor-driven auxiliary feedwater
train out of service on July 23
A emergency diesel generator with the B emergency diesel generator out of service
on August 6
B residual heat removal system with the A residual heat removal system inoperable
on September 17
2
To evaluate the operability of the selected trains or systems under these conditions, the
inspectors reviewed valve and power alignments by comparing observed positions of
valves, switches, and electrical power breakers to the procedures and drawings listed in
the Attachment.
b.
Findings
No findings of significance were identified.
1R05
Fire Protection
a.
Inspection Scope
For the six areas identified below, the inspectors reviewed the licensees control of
transient combustible material and ignition sources, fire detection and suppression
capabilities, fire barriers, and any related compensatory measures, to verify that those
items were consistent with Final Safety Analysis Report (FSAR) Section 9.5.1, Fire
Protection System, and FSAR Appendix 9.5.A, Fire Hazards Analysis. The inspectors
walked down accessible portions of each area and reviewed results from related
surveillance tests, to verify that conditions in the area was consistent with the description
of the area in the FSAR. Documents reviewed are listed in the Attachment.
Reactor Auxiliary Building 236 foot elevation Auxiliary Feedwater (AFW) and
Component Cooling Water (CCW) pump area (1-A-3-PB)
Switchgear room A (1-A SWBRA)
Switchgear room B (1-A-SWGRB)
Main control room (12-A-CR)
Computer room, process instrument control cabinets, and control-rod-drive
circuit cabinets (12-A-CRC1)
Vital battery room B (1-A-BATB)
Also, to evaluate the readiness of the licensees personnel to prevent and fight fires, the
inspectors observed fire brigade performance during an unannounced fire drill in the C
CSIP room on August 29.
b.
Findings
No findings of significance were identified.
1R11
Licensed Operator Requalification
a.
Inspection Scope
On August 27, the inspectors observed licensed-operator performance during
requalification simulator training, to verify that operator performance was consistent with
expected operator performance, as described in Exercise Guide EOP-SIM-17.104. This
training tested the operators ability to deal with reactor coolant pump trouble, safety
injection failure, and a main steam line break.
3
The inspectors focused on clarity and formality of communication, use of procedures,
alarm response, control board manipulations, group dynamics and supervisory
oversight.
The inspectors observed the post-exercise critique to verify that the licensee had
identified deficiencies and discrepancies that occurred during the simulator training.
b.
Findings
No findings of significance were identified.
1R12
Maintenance Effectiveness
a.
Inspection Scope
The inspectors reviewed one degraded SSC/function condition to verify the licensees
handling of the condition in accordance with 10CFR50, Appendix B, Criterion XVI,
Corrective Action, and 10CFR50.65, Maintenance Rule. The specific condition involved
multiple failures of 1CP-6, an isolation damper in the containment purge system, as
reported in Action Request (AR) 88929.
The inspectors focused on the following attributes:
Appropriate work practices,
Identifying and addressing common cause failures,
Scoping in accordance with 10 CFR 50,65(b),
Characterizing reliability issues (performance),
Charging unavailability (performance),
Trending key parameters (condition monitoring),
10 CFR 50,65(a)(1) or (a)(2) classification and reclassification, and
Appropriateness of performance criteria for SSCs/functions classified (a)(2)
and/or appropriateness and adequacy of goals and corrective actions for
SSCs/functions classified (a)(1).
b.
Findings
No findings of significance were identified.
1R13
Maintenance Risk Assessments and Emergent Work Evaluation
a.
Inspection Scope
To verify that the licensee performed adequate risk assessments and implemented
appropriate risk management actions when required by 10CFR50.65(a)(4), the
inspectors reviewed the licensees risk assessments and the actions used to manage
risk for the plant configurations associated with the four activities listed below. For
emergent work, the inspectors also verified that any increase in risk was promptly
assessed, and that appropriate risk management actions were promptly implemented.
4
The work week of June 30, including the A emergency chilled water system
outage on July 2
The work week of July 28, including re-evaluation of plant risk for thunderstorm
warnings
The work week of September 8, including the RHR/CS pump room air handler
being out of service
The work week of September 15, including re-evaluation of plant risk for the
approach of Hurricane Isabel
b.
Findings
No findings of significance were identified.
1R14
Operator Performance During Non-Routine Evolutions and Events
a.
Inspection Scope
Following the manual reactor trip of August 17, 2003, the inspectors responded to the
site and observed plant instruments, reviewed plant logs and interviewed operators to
verify that the operators response was in accordance with post-trip procedures, plant
operating procedures and related training. Documents reviewed are listed in the
Attachment.
b.
Findings
No findings of significance were identified.
1R15
Operability Evaluations
a.
Inspection Scope
The inspectors reviewed three operability determinations addressed in response to the
ARs listed below. The inspectors assessed the accuracy of the evaluations, the use
and control of any necessary compensatory measures, and compliance with the
Technical Specifications (TS). The inspectors compared the justification made in the
determination to the requirements from the TS, the FSAR, and the associated design-
basis documents, to verify that operability was properly justified, and that the subject
component remained available, such that no unrecognized increase in risk occurred.
Documents reviewed are listed in the Attachment.
AR 96373, HNP Action Plan for containment sump level transmitter LT-7161A
AR 103527103527 Relay Failure on the 1B emergency safeguards sequencer
AR 95977, Through wall leak on service water line near valve 1SW-118
b.
Findings
No findings of significance were identified.
5
1R19
Post Maintenance Testing
a.
Inspection Scope
For the five post-maintenance tests listed below, the inspectors witnessed the test
and/or reviewed the test data, to verify that test results adequately demonstrated
restoration of the affected safety functions described in the FSAR and TS.
OP-155, Diesel Generator Emergency Power System, following repair of a fuel
line leak on July 1
ORT-1512, Essential Chilled Water Turbopak Units Quarterly Inspection/Checks
Modes 1-6, following routine maintenance on the train A essential chilled water
chiller on July 16
OST-1008, 1A-SA RHR Pump Operability Quarterly Interval Modes 1-2-3,
following maintenance on 1-RH-31, A RHR Pump Mini Flow Valve
OST-1073, 1B-SB Emergency Diesel Generator Operability Test Monthly Interval
Modes 1-2-3-4-5-6, following routine maintenance on the train B emergency
diesel generator on August 6
OPT-1014, Turbine Valve Test Quarterly Interval Modes 1-5, following a
firmware modification to the digital electro-hydraulic system
b.
Findings
No findings of significance were identified.
1R22
Surveillance Testing
a.
Inspection Scope
For the four surveillance tests identified below, the inspectors witnessed testing and/or
reviewed test data to verify that the systems, structures, and components involved in
these tests satisfied the requirements described in the TS and the FSAR, and that the
tests demonstrated that the SSCs were capable of performing their intended safety
functions.
MST-I0207, Refueling Water Storage Tank Level (L-0993) Operational Test
OST-1211*, Auxiliary Feedwater Pump 1A-SA Operability Test Quarterly Interval
Modes 1-4
MST-I0151, Steam Generator C Narrow Range Level Loop (L-0496) Operational
Test
OST-1122, Train A 6.9 kV Emergency Bus Undervoltage Trip Actuating Device
Operational Test and Contact Check Modes 1-6
- This procedure included inservice testing requirements.
b.
Findings
No findings of significance were identified.
6
1EP6
Drill Evaluation
a.
Inspection Scope
The inspectors observed an operator training evolution conducted on August 27, to
verify licensee self-assessment of classification, notification, and protective action
recommendation development in accordance with NEI 99-02, Regulatory Assessment
Indicator Guideline, Rev. 2.
b.
Findings
No findings of significance were identified.
4.
OTHER ACTIVITIES
August 17 Reactor Trip
a.
Inspection Scope
Following a manual reactor trip that occurred on August 17, 2003 from 100 percent
power, due to a loss of the A condensate pump; the inspectors reviewed the licensees
actions, observed plant parameters for mitigating systems and fission product barriers,
and assessed licensee event classification and reporting. The inspectors later reviewed
the post-trip/safeguards actuation report to verify that plant response was as expected
and to verify that plant equipment abnormalities were identified and corrected prior to
plant startup. Refer to Section 1R14 for additional information. ocuments reviewed are
listed in the Attachment.
b.
Findings
No findings of significance were identified.
4OA6 Meetings, Including Exit
On October 6, 2003, the resident inspectors presented the inspection results to
Mr. James Scarola and other members of his staff. The inspectors confirmed that
proprietary information was not provided or examined during the inspection.
Attachment
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
D. Braund, Security Superintendent
J. Briggs, Superintendent, Environmental and Chemical
J. Caves, Licensing Supervisor
F. Diya, Superintendent, System Engineering (Acting Engineering Support Services
Mgr.)
R. Duncan, Director Site Operations
W. Gurganious, Nuclear Assessment Manager
E. McCartney, Training Manager
G. Miller, Maintenance Manager
T. Morton, Manager Support Services
T. Natale, Outage and Scheduling Manager
G. Olive, Lead Nuclear Security Specialist
T. Pilo, Emergency Preparedness Supervisor
J. Scarola, Harris Plant Vice President
G. Simmons, Superintendent, Radiation Control
B. Waldrep, Harris Plant General Manager
M. Wallace, Senior Specialist, Licensing
E. Wills, Operations Manager
NRC personnel
P. Fredrickson, Chief, Reactor Projects Branch 4
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
None
LIST OF DOCUMENTS REVIEWED
1R04
Equipment Alignment
Partial System Walkdown
Emergency diesel generator system
Procedure OP-155, Diesel Generator Emergency Power System
Drawing 2165-S-563, Simplified Flow Diagram Diesel Fuel Oil System, Unit 1
Drawing 2165-S-633S01, Simplified Flow Diagram Emergency Diesel Generator
Lube Oil and Air Intake & Exhaust System - Unit 1.
Drawing 2165-S-0633S02, Simplified Flow Diagram Emergency Diesel Generator
1A-SA & 1B-SB Jacket Water System Unit 1
2
Drawing 2165-S-0633S03, Simplified Flow Diagram Emergency Diesel Generator
1A-SA & 1B-SB Fuel Oil and Drainage Systems Unit 1
Drawing 2165-S-0633S04, Simplified Flow Diagram Emergency Diesel Generator
1A-SA & 1B-SB Starting Air System Unit 1
Auxiliary Feedwater System
Procedure OP-137, Auxiliary Feedwater System
Drawing 2165-S-0544, Simplified Flow Diagram Feedwater System Unit 1"
Residual Heat Removal System
Drawing 2165-S-LATER, Simplified Flow Diagram Residual Heat Removal System
Unit 1"
1R05
Fire Protection
Results from recent completions of the following procedures:
FPT-1301, Hose Rack Inspection Auxiliary Building - Quarterly Interval Modes All
FPT-3204, Fire Detector Functional Test Local Fire Detector Panel 4 -12 Month
Interval
FPT-3151, Fire Protection Periodic Test Fire Extinguisher Inspection Auxiliary
Building - Monthly Interval
FPT-3426, Fire Damper Inspection 18 Month Interval RAB 236 Elevation
Other Documents
Fire Preplan FPP-012-02-RAB A09-4
Fire Preplan FPP-012-02-RAB A34-6
Fire Preplan FPP-012-02-RAB A35-6
Fire Preplan FPP-012-02-RAB A38-6
Fire Preplan FPP-012-02-RAB A51-7
Fire Preplan FPP-012-02-RAB A52-7
Fire Preplan FPP-012-02-RAB A53-7
Fire Preplan FPP-012-02-RAB A55-7
1R13
Maintenance Risk Assessments and Emergent Work Evaluation
Procedures
Operations Work Procedure (OWP), OWP-HVAC, Emergency Ventilation
Other Documents
Calculation 9-TMC-1
Calculation HNP-F/PSA-0058
3
1R14
Personnel Performance During Nonroutine Plant Evolutions and Events and Section
4OA3: Event Follow-up
Procedures
Emergency Operating Procedure (EOP), EOP-PATH-1, Path -1
Abnormal Operating Procedure (AOP), AOP-10, Feedwater Malfunctions
EOP-EPP-004, Reactor Trip Response
Other Documents
OMM-4 Post-trip/Safeguards Review Package for August 17, 2003 Manual Reactor Trip
1R15
Operability Evaluations
Procedures
Operations Surveillance Test (OST), OST-1021, Daily Surveillance Requirements,
Daily Surveillance Log of containment sump level transmitter LIT-01CT-7161ASA
Maintenance Surveillance Test (MST), MST-I0198, Containment Reactor Cavity
Sump NR Level Loop (LM-7161A) Calibration
Operating Procedure (OP), OP-163, Plant Computer
Other Documents
FSAR Section 5.2.5.3.1
AR 96373, HNP Action Plan for LT7161A
DBD-141, Plumbing and Drainage System
Data Results of containment sump level transmitter compensatory actions July 3
through September 20, 2003