ML031320011
| ML031320011 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 05/08/2003 |
| From: | Casto C Division Reactor Projects II |
| To: | Moyer J Carolina Power & Light Co |
| References | |
| IR-03-008 | |
| Download: ML031320011 (35) | |
See also: IR 05000261/2003008
Text
May 8, 2003
Carolina Power & Light Company
ATTN:
Mr. J. W. Moyer
Vice President
H. B. Robinson Steam Electric Plant Unit 2
3581 West Entrance Road
Hartsville, SC 29550
SUBJECT:
H. B. ROBINSON STEAM ELECTRIC PLANT - NRC INSPECTION REPORT
50-261/03-08
Dear Mr. Moyer:
On October 25, 2002, the NRC completed an inspection regarding the application for license
renewal for your Robinson facility. The enclosed report documents the inspection findings,
which were discussed on April 4, 2003, with you and other members of your staff in an exit
meeting open for public observation at the Hartsville Memorial Library.
The purpose of this inspection was an examination of activities that support the application for a
renewed license for the Robinson facility. The inspection consisted of a selected examination
of procedures and representative records, and interviews with personnel regarding the process
of scoping and screening plant equipment to select equipment subject to an aging management
review. For a sample of plant systems, inspectors performed visual examination of accessible
portions of the systems to observe any effects of equipment aging.
The inspection concluded that the scoping and screening portion of the license renewal
activities were conducted as described in the License Renewal Application and that
documentation supporting the application is in an auditable and retrievable form. With the
exception of the items identified in this report, your scoping and screening process was
successful in identifying those systems, structures, and components required to be considered
for aging management.
In accordance with 10 CFR 2.790 of the NRCs "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).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the
Public Electronic Reading Room).
Should you have any questions concerning this letter, please contact Caudle Julian at
404-562-4603.
Sincerely,
\\RA\\
Charles A Casto, Director
Division of Reactor Safety
Docket Nos:. 50-261
License Nos:. DPR-23
cc: See page 3
3
cc:
Mr. William D. Johnson
Vice President and Corporate Secretary
Carolina Power & Light Company
Post Office Box 1551
Raleigh, NC 27602
Ms. Peggy Force
Assistant Attorney General
State of North Carolina
Post Office Box 629
Raleigh, NC 27602
U.S. Nuclear Regulatory Commission
Resident Inspectors Office
H. B. Robinson Steam Electric Plant
2112 Old Camden Road
Hartsville, SC 29550
Mr. T. P. Cleary
Plant General Manager
Carolina Power & Light Company
H. B. Robinson Steam Electric Plant, Unit
No. 2
3581 West Entrance Road
Hartsville, SC 29550
Mr. Chris L. Burton
Director of Site Operations
Carolina Power & Light Company
H. B. Robinson Steam Electric Plant, Unit
No. 2
3581 West Entrance Road
Hartsville, SC 29550
Public Service Commission
State of South Carolina
Post Office Drawer 11649
Columbia, SC 29211
Mr. C. T. Baucom
Supervisor, Licensing/Regulatory Programs
Carolina Power & Light Company
H. B. Robinson Steam Electric Plant
Unit No. 2
3581 West Entrance Road
Hartsville, SC 29550
Ms. Beverly Hall, Acting Director
N.C. Department of Environment
and Natural Resources
Division of Radiation Protection
3825 Barrett Dr.
Raleigh, NC 27609-7721
Mr. Robert P. Gruber
Executive Director
Public Staff - NCUC
4326 Mail Service Center
Raleigh, NC 27699-4326
Mr. R. Mike Gandy
South Carolina Department of Health
and Environmental Control
Division of Radioactive Waste Management
2600 Bull Street
Columbia, SC 29201
Mr. James W. Holt, Manager
Performance Evaluation and
Regulatory Affairs CPB 7
Carolina Power & Light Company
Post Office Box 1551
Raleigh, NC 27602-1551
Mr. John H. ONeill, Jr.
Shaw, Pittman, Potts & Trowbridge
2300 N Street, NW.
Washington, DC 20037-1128
Mr. B. L. Fletcher III
Manager - Regulatory Affairs
Carolina Power & Light Company
H. B. Robinson Steam Electric Plant
Unit No. 2
3581 West Entrance Road
Hartsville, SC 29550-0790
Mr. Alan P. Nelson
Nuclear Energy Institute
1776 I Street, NW., Suite 400
Washington, DC 20006-3708
4
cc cont:
Talmage B. Clements
Manager - License Renewal
Carlina Power and Light Company
410 South Wilmington Street
Raleigh, NC 27602
Mr. Roger A. Stewart
Carolina Power and Light Company
H. B. Robinson Steam Electric Plant, Unit
No. 2
3581 West Entrance Road
Hartsville, SC 29550
U. S. NUCLEAR REGULATORY COMMISSION
REGION II
Docket No:
50-261
License No:
Report No:
50-261/03-08
Licensee:
Carolina Power and Light Company (CPL)
Facility:
H. B. Robinson Steam Electric Plant, Unit 2
Location:
3581 West Entrance Road
Hartsville, SC 29550
Dates:
March 31 - April 4, 2003
Inspectors:
W Bearden, Reactor Inspector
M. Maymi, Reactor Inspector
R. Moore, Reactor Inspector
M. Scott, Reactor Inspector
K. Van Doorn, Reactor Inspector
H. Wang, Operations Engineer, NRR
Approved by:
Caudle Julian
Team Leader
Division of Reactor Safety
TABLE OF CONTENTS
Summary of Findings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
I
Report Details . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1
I.
Inspection Scope . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1
II.
Findings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1
A. Evaluation of Scoping and Screening of Mechanical Systems . . . . . . . . . . . . 1
1. Reactor Coolant System (RCS) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2
2. Chemical and Volume Control System . . . . . . . . . . . . . . . . . . . . . . . . 3
3. Spent Fuel Pool Cooling System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
4. Residual Heat Removal System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
5. Safety Injection System (SI) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
6. Diesel Generator System (DG) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
7. Dedicated Shutdown Diesel Generator . . . . . . . . . . . . . . . . . . . . . . . . 4
8. EOF/TSC Security Diesel Generator . . . . . . . . . . . . . . . . . . . . . . . . . . 4
9. Fuel Oil System (FO) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
10. Component Cooling Water (CCW) . . . . . . . . . . . . . . . . . . . . . . . . . . 5
11. Service Water (SW)
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
12. Instrument and Service Air (IA, SA) . . . . . . . . . . . . . . . . . . . . . . . . . . 5
13. Containment Spray (CS) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6
14. Auxiliary Feedwater System (AFW) . . . . . . . . . . . . . . . . . . . . . . . . . . 6
15. Main Feedwater System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6
16. Containment Isolation System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6
17. Post Accident Sampling . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7
18. Heating, Ventilation, and Air Conditioning . . . . . . . . . . . . . . . . . . . . . 7
19. HVAC - Containment Building . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7
20. HVAC - Control Room Area . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8
21. HVAC - Fuel Handling Building . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8
22. Emergency Diesel Generator Room CARDOX System . . . . . . . . . . . 8
23. HVAC - Radwaste Facility . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8
24. HVAC - Turbine Building . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8
B. Evaluation of Scoping and Screening of Electrical Systems . . . . . . . . . . . . . . 8
C. Evaluation of Scoping and Screening of Structural Components . . . . . . . . . 10
1. Reactor Containment Building . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10
2. Switchyard Relay Building, Switchyard and Transformer Structures . 10
3. Reactor Auxiliary Building . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11
4. Pipe Restraint Tower . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11
5. Plant Vent Stack . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12
6. Intake Structure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12
7. East Personnel Access Portal . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12
8. West Personnel Access Portal . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13
9. Security Emergency Diesel Generator Building . . . . . . . . . . . . . . . . . 13
10. Fuel Handling Building . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13
11. Electrical Manholes and Duct Banks . . . . . . . . . . . . . . . . . . . . . . . . 13
12. Reservoir and Dam . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14
13. Tech Support Center/Emergency Operations Facility . . . . . . . . . . . 14
14. Concrete Trenches . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14
15. Tank Foundations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14
D. Evaluation of Scoping and Screening of Fire Protection Systems
. . . . . . . . 15
E. Visual Observations of Plant Equipment in Containment . . . . . . . . . . . . . . . 15
Attachment 1 Supplemental Information . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17
Attachment 2 H. B. Robinson License Renewal Inspection Plan . . . . . . . . . . . . . . . . . . . . . . . . 22
Attachment 3 List of Acronyms Used . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 26
I
SUMMARY OF FINDINGS
IR 05000261-03-08; 3/31-4/4/20032; Carolina Power and Light Company, H. B. Robinson Steam
Electric Plant, Unit 2. License Renewal Inspection Program, Scoping and Screening.
This inspection of License Renewal (LR) activities was performed by six regional office
engineering inspectors, and one staff member from the office of Nuclear Reactor Regulation.
The inspection program followed was NRC Manual Chapter 2516 and NRC Inspection Procedure 71002. This inspection did not identify any findings as defined in NRC Manual Chapter 0612.
The overall conclusion of this inspection was that the license renewal scoping and screening
process was successful. The inspection did reveal the following discrepancies in the applicants
supporting documentation.
Three examples were identified where there was an inconsistency between the application, the
boundary drawing, and the calculation that supports the applicants conclusion. The applicant
wrote a plant Action Request (AR) number 89349 to initiate corrective action to correct the
inconsistencies.
Regarding the auxiliary feedwater system, the inspectors questioned why the backup Deep Well
water supply was not in scope for license renewal. NRR has asked the same question via a
Request for Additional Information (RAI). Inspectors will review the applicants answer to the RAI
during a future inspection.
Regarding the diesel fuel oil system, applicants calculation RNP-L/LR-0006 states that the unit 1
fuel oil tanks and piping used to transfer oil to unit 2 for long term operation of the emergency
diesel generators are in scope. However the boundary drawings didnt depict the transfer piping
as being in scope. The inspectors concluded that the piping should be in scope. The applicant
acknowledged the inspectors comments and will resolve the discrepancy.
Applicants calculation RNP-L/LR-0396 was intended to explain the process used for scoping and
screening of Criterion 2 piping. Criterion 2 are cases where non-safety related piping (NSR)
located in the vicinity of safety related (SR) components might cause damage to SR components
if they failed due to aging. The inspectors had extensive discussion with the applicant to
understand the process and to agree with the applicants conclusions. However calculation 0396
did not clearly describe the process or conclusions and inspectors identified several minor errors
in the calculation. The inspectors stated that the applicant should revise calculation 0396 to more
clearly explain their process and conclusions.
The inspectors identified several instances where the applicants proposed responses to NRR
written RAI questions appeared to be unclear or incomplete. The applicant agreed to consider
the inspectors comments when completing their response to the RAIs.
In walking down plant systems and examining plant equipment the inspectors found no significant
adverse conditions and it appears plant equipment was being maintained adequately.
1
Report Details
I.
Inspection Scope
This inspection was conducted by NRC Region II inspectors and members of the NRR staff to
interview applicant personnel and to examine a sample of documentation which supports the
license renewal application (LRA). This inspection reviewed the results of the applicants scoping
of plant systems and screening of components within those systems to identify the list of
components that need evaluation for aging management. The team selected a sample of plant
systems, structures, and components (SSC) from the LRA scoping results to verify the adequacy
of the applicants scoping and screening documentation and implementation activities. For the
selected in-scope systems/structures, the associated boundary drawings, and the active/passive
and short/long lived determinations of the selected SSCs were reviewed to confirm the accuracy
of the applicants results. In addition to the in-scope systems and structures, some systems that
the applicant had determined not to be in scope for license renewal were selected for inspection.
The inspectors reviewed supporting documentation and interviewed applicant personnel to
confirm the accuracy of the LRA conclusions. The SSCs selected for review during this
inspection are listed in Attachment 2 to this report. For a sample of plant systems, inspectors
performed visual examination of accessible portions of the systems to observe any effects of
equipment aging.
II.
Findings
A. Evaluation of Scoping and Screening of Mechanical Systems
The inspectors evaluated the applicants scoping and screening process for mechanical
components by reviewing a number of plant systems that the applicant determined to be within
the scope of license renewal (LR). The applicant performed scoping at the system level by first
identifying safety-related mechanical systems via review of the equipment data base (EDB). In
addition, through review of the EDB and other license basis information, non-safety-related
mechanical systems which could adversely affect safety-related systems were identified and
systems committed to support the five NRC regulated events in 54.4(a)(3) were identified.
After system scoping, screening was accomplished by: establishment of LR system boundaries
by creating from official station drawings highlighted license renewal boundary flow diagram
drawings: identifying components and component groups subject to an aging management
review using a list of all passive, long-lived, mechanical components; and identification of
intended function(s) of each mechanical component. The screening process and results were
documented in individual system LR Screening Calculations.
Subsequent to the initial LR application, additional NRC guidance was issued for consideration of
the effects of NSR systems on SR systems, such as via spray, leakage, pipe whip, jet
impingement, flooding, and displacement/falling. The inspectors reviewed the applicants
methodology for inclusion of NSR mechanical systems in scope which could affect SR systems.
In addition, the inspectors conducted field walkdowns in various areas of the plant containing SR
systems to observe for NSR systems to confirm appropriate NSR systems had been included for
LR aging management. During these walkdowns the inspectors also observed equipment
material condition. Additional walkdowns are planned for subsequent inspections. The
applicants methodology consisted of: determining all areas where SR and NSR systems were
located; considering all NSR systems within these areas to be in scope for LR; evaluating via
2
documentation and walkdowns which NSR systems could damage SR systems for screening
considerations. For those systems which had portions which were NSR of the same
materials/environs as the SR portion and had existing credited aging management programs, the
applicant simply added the NSR portion of the system for specific areas as requiring aging
management via the existing program. For a few cases the applicant screened in a portion of a
NSR system as requiring aging management, e.g. a portion of the Potable Water System which
was located near some SR switchgear. No significant material condition problems were noted
during the field observations and the inspectors concluded that the applicant had added the
appropriate NSR equipment for aging management.
Applicants calculation RNP-L/LR-0396 was intended to explain the process used for scoping and
screening of Criterion 2 piping. Criterion 2 are cases where non-safety related piping located in
the vicinity of safety related components might cause damage to SR components if they failed
due to aging. The inspectors review of the applicants calculation disclosed that it was not clear
in some cases regarding which NSR portions of systems were added for aging management.
The inspectors had extensive discussion with the applicant to understand the process and to
agree with the applicants conclusions. However calculation 0396 did not clearly describe the
process or conclusions and inspectors identified several minor errors in the calculation. This
document was in error regarding the addition of the equipment in the Spent Fuel Pit Room for
aging management and listing portions of the Auxiliary Steam System as being in containment.
The inspectors stated that the applicant should revise calculation 0396 to more clearly explain
their process and conclusions. The applicant initiated Action Request (AR) No. 89608 to track
correction/clarification of this document.
Areas containing the following systems/structures were observed for appropriate
scoping/screening for NSR effects on SR systems:
Chemical and Volume Control System
Spent Fuel Pool Cooling System
Chemical Feed System (partial)
Component Cooling Water System
Auxiliary Feedwater System
Containment Isolation System
The following mechanical systems were reviewed:
1. Reactor Coolant System (RCS) [including Reactor Vessel and Internals; Reactor Vessel Level
Instrumentation/Inadequate Core Cooling Monitor (ICCM) System; Steam Generator (SG); and
two SG associated pressure boundary systems, Steam Generator Blowdown and Chemical Feed]
These systems are designed to contain and support the nuclear fuel, contain the reactor coolant,
and transfer heat produced in the reactor to the steam and power conversion systems for the
production of electricity. The applicant essentially considered all of the RCS, Reactor Internals,
ICCM System, and SGs to be in scope of LR except for some components not required for the
LR function. The systems associated with SGs for pressure boundary purposes were also
included in scope of LR. The inspectors reviewed LR boundary drawings, design basis
information, the Updated Final Safety Analysis Report (UFSAR), engineering documentation,
system/structure scoping worksheets, screening calculations, and station blackout flow path
drawings. The inspectors also conducted field observations of portions of the Chemical Feed
System. The inspectors concluded that the applicant had performed scoping and screening for
3
these systems and identified the mechanical components subject to aging management in
accordance with the methodology described in the LRA and the rule.
2. Chemical and Volume Control System
The Chemical and Volume Control System functions to provide reactor coolant pump seal
injection, maintain proper RCS inventory, adjust RCS boron concentration, maintain RCS
chemistry control, and RCS degasification. Essentially all of the system has been included for LR
aging management due to being SR or NSR affecting SR systems. The inspectors reviewed LR
boundary drawings, design basis information, the UFSAR, system/structure scoping worksheets,
and screening calculations. The inspectors also conducted field observations of the system. The
inspectors concluded that the applicant had performed scoping and screening for this systems
and identified the mechanical components subject to aging management in accordance with the
methodology described in the LRA and the rule.
3. Spent Fuel Pool Cooling System
The Spent Fuel Pool Cooling System functions to remove decay heat from the spent fuel pool
and to maintain pool water chemistry which are not functions for LR. Portions are credited for
postulated fires and station blackout. The applicant included the portions of the system for fires
and station blackout, the portion of the system which interfaces with Component Cooling Water,
and NSR portions in the Safety Injection Pump Room and Demineralizers Room for aging
management. The inspectors reviewed the LR boundary drawing, design basis information,
system/structure scoping worksheets, and screening calculations. The inspectors also conducted
field observations of the system. The inspectors concluded that the applicant had performed
scoping and screening for this systems and identified the mechanical components subject to
aging management in accordance with the methodology in the LRA and the rule.
4. Residual Heat Removal System
The Residual Heat Removal System functions to remove heat from the RCS during normal plant
shutdown conditions, provides borated water to RCS during a design basis accident, and
recirculates water from the containment sump during a postulated loss of coolant accident.
Essentially all of this system was determined to require aging management. The inspectors
reviewed LR boundary drawings, system/structure scoping worksheets, and screening
calculations. The inspectors concluded that the applicant had performed scoping and screening
for these systems and identified the mechanical components subject to aging management in
accordance with the methodology described in the LRA and the rule.
5. Safety Injection System (SI)
The SI system provides adequate emergency core cooling following a postulated design basis
accident. The SI system performs the funtions of : passive accumulator injection, active safety
injection, and residual heat removal recirculation of water from the containment sump. The
primary purpose of the system is to deliver cooling water to the reactor core in the event of a loss-
of-coolant accident. The system also provides a source of borated water for reactivity control. The
applicant included all of the safety related portion of the system in scope for license renewal. The
inspectors reviewed the system scoping and screening documents, license renewal boundary
drawings, the UFSAR, and the SI system description. The inspectors also performed a walkdown
of accessible portions of the system. The inspectors concluded that the applicant had performed
4
scoping and screening for the SI system in accordance with the methodology described in the
H.B. Robinson LRA and the rule.
6. Diesel Generator System (DG)
The DG system provides AC power to the onsite electrical distribution system in case normal AC
power is lost to assure the capability for a safe plant shutdown. The DG support systems include
the Starting Air Subsystem, Lube Oil Subsystem, Jacket Water Cooling Subsystem, Scavenging
Air Subsystem, Scavenging Air Cooling Subsystem, Diesel Engine Fuel Oil Subsystem, and the
Diesel Exhaust Subsystem. Mechanical components included in the LR scope for aging
management review included heat exchangers, regulators, pumps, filters, strainers, exhaust
silencer, tanks, flow orifices and elements, valves, piping, tubing and fittings. The inspectors
reviewed the system scoping and screening documents, license renewal boundary drawings, the
UFSAR, and the DG system description. The inspectors also performed a walkdown of
accessible portions of the system. The inspectors concluded that the applicant had performed
scoping and screening for the DG system in accordance with the methodology described in the
H.B. Robinson LRA and the rule.
7. Dedicated Shutdown Diesel Generator (DSDG)
The DSDG provides an alternate AC power source to assure the capability for safe plant
shutdown following a fire or total loss of all AC power (Station Blackout). The skid-mounted, self-
contained DSDG is a component of the Dedicated Shutdown Electrical System. The inspectors
reviewed the system scoping and screening documents, license renewal boundary drawings, the
UFSAR, and the DSDG system description. The inspectors also performed a walkdown of
accessible portions of the system.
The inspectors observed that the screening calculation RNP-L/LR-0115 and the license renewal
application says that an air filter and two relief valves on the air start system are in scope for
license renewal. But a note in the calculation says the filter and valves are not in LR scope and
the components are not shown as being in scope on the boundary drawing. This is a
contradiction that the applicant included in AR 89349 to resolve.
8. EOF/TSC Security Diesel Generator
The EOF/TSC Security Diesel Generator provides backup electrical power to the Emergency
Operations Facility/Technical Support Center Building and security systems upon loss of the
normal power supplies. The backup electrical power supplied to security lighting in outside areas
is relied on for performance of actions required for fire protection safe shutdown, thus the diesel
is in the scope of LR. Mechanical components included in the LR scope for aging management
review included filters, radiator, exhaust silencer, heaters, ductwork, valves, piping, tubing and
fittings. The inspectors reviewed the system scoping and screening documents, license renewal
boundary drawings, and the EOF/TSC Security Diesel Generator system description. The
inspectors concluded that the applicant had performed scoping and screening for the system in
accordance with the methodology described in the Robinson LRA and the rule.
9. Fuel Oil System (FO)
The FO System supplies fuel oil to the Emergency Diesel Engines, the Dedicated Shutdown
Diesel Engine, and the Diesel Engine-Driven Fire Pump from fuel oil storage tanks on site. The
FO System also provides fuel oil to the EOF/TSC Security Diesel Generator. The FO system
5
provides a fuel oil storage capacity sufficient to operate the Emergency Diesel Generators at full
load for a period of seven days in accordance with Technical Specification requirements if oil can
be transfered from Unit 1 storage tanks to Unit 2. The inspectors reviewed the system scoping
and screening documents, license renewal boundary drawings, Technical Specification Bases,
and an operating procedure. The inspectors also performed a walkdown of some portions of the
system.
Regarding the diesel fuel oil system, applicants calculation RNP-L/LR-0006 says that the unit 1
fuel oil tanks and piping used to transfer oil to unit 2 for long term operation of the emergency
diesel generators are in scope. However the boundary drawings didnt depict the transfer piping
as being in scope. Also calculation RNP-L/LR-0121 reflects that the transfer piping is not in
scope. The inspectors stated their opinion that the piping should be in scope. The applicant
agreed to consider the inspectors comments and resolve the discrepancy.
10. Component Cooling Water (CCW)
This closed loop cooling system removes heat from several safety-related systems, non-safety
systems, and components. At the service water to component cooling heat exchanger heat is
removed by the cooler Service Water. With minor exception, the entire system is within license
renewal scope. The inspectors examined the portions of the system not included in scope and
detailed system drawings indicating component locations that were not in scope to verify that
those portions would not have adverse interaction with other nearby systems. The inspectors
reviewed the license renewal boundary drawings, system descriptions, applicable UFSAR
sections, scoping calculations, and application details. The inspectors determined that the
system was appropriately scoped in the application and associated boundary drawings.
11. Service Water (SW)
SW is a open cycle cooling loop that removes heat from various safety-related systems, non-
safety-related systems, and components. With normal exceptions (turbine building, air
compressor systems cooling, and auxiliary boiler heat loads), the system is within scope under
license renewal. The inspectors reviewed the license renewal boundary drawings, system
descriptions, applicable UFSAR sections, scoping calculations, and application details. The
inspectors determined that the system was appropriately scoped in the application and
associated boundary drawings.
12. Instrument and Service Air (IA, SA)
These air systems provide air for normal system operations and outage uses. Their critical
functions for other off normal conditions identified during the licensee renewal scoping review are
pressure boundary interface for other systems and containment penetration integrity. Off-normal
gas motive force for critical component operation (e.g., steam generator power operated relief
valves) is provided by nitrogen systems, the not-in-scope instrument air, or by instrument air
contained in pressurized accumulators isolated by check valves (e.g., main steam isolation
valves). The inspectors reviewed the license renewal boundary drawings, system descriptions,
applicable UFSAR sections, generic interface documents, scoping calculations, and application
details. The inspectors determined that the systems were appropriately scoped in the application
and associated boundary drawings.
6
13. Containment Spray (CS)
The CS system in conjunction with the Containment Air Recirculation System limit the
temperature and pressure in containment following a steam line break or loss of coolant accident
to less than design values. The CS systems pumps and spray nozzles can deluge the
containment with borated water combine with educted sodium hydroxide during its injection
phase. The system can be cooled by the residual heat removal system for long term containment
cooling. The inspectors reviewed the license renewal boundary drawings, system descriptions,
applicable UFSAR sections, scoping calculations, and applications details. The inspectors
determined that the systems were appropriately scoped in the application and associated
boundary drawings.
14. Auxiliary Feedwater System (AFW)
This system supplies feedwater to the steam generators when normal feedwater sources are not
available. The components included in the LR scope for aging management review included the
Condensate Storage Tanks as the normal water source and the service water system as the
safety related, assured source. The Deep Well pumps are an alternate source referenced in the
UFSAR. The inspectors questioned why the Deep Well pumps and piping were not included in
the LR scope. The applicants position was that this equipment does not provide a safety related
water source and therefore does not meet the LR scoping criteria. This issue is addressed in RAI
2.3.3.8-1 and 2.3.4.9-1 which is presently under review by the NRC.
Other in scope equipment is identified in LRA table 2.3-29. The inspectors reviewed the
applicants identification and resolution of criterion 2 (NSR equipment potentially affecting LR in-
scope equipment) related to the AFW system, field verified these conditions where possible, and
concluded the resolutions were acceptable. The inspectors reviewed the system scoping and
screening documents, design basis information, applicable UFSAR sections and the system
boundary drawings. The inspectors concluded that the applicant had performed scoping and
screening for this system in accordance with the LRA and the Rule.
15. Main Feedwater System
The main feedwater system provides pre-heated, high pressure feedwater to the steam
generators under normal operating conditions. The license renewal function of the system is to
provide isolation of the feedwater and steam generator blow down following a postulated loss of
coolant or steam line break event. The components identified as within LR scope and requiring
aging management review are identified in Table 2.3-28 of the application. The inspectors
reviewed the system scoping and screening documents, design basis information, applicable
UFSAR sections, and boundary drawings. The inspectors concluded the Applicant had
performed scoping and screening for this system in accordance with the LRA and the Rule.
16. Containment Isolation System
The Containment Isolation System is an engineered safety feature that provides for the closure
integrity of containment penetrations in the event of a reactor accident to prevent leakage of
uncontrolled or unmonitored radioactive materials to the environment. The following systems
have only the license renewal function of containment isolation:
Post Accident Hydrogen
Service Air System
7
Process/Area Radiation Monitoring
Containment Pressure Relief
Containment Vacuum Breaker
Containment Purge
Containment Vapor and Pressure Sampling
Liquid Waste Processing
Penetration Pressurization Local Leak Rate Test
Isolation Valve Seal Water.
Table 2.3-6 of the Application identified the components of these systems which are in scope for
LR and require aging management review. The inspectors reviewed the system scoping and
screening documents, design basis information, applicable UFSAR sections and the boundary
drawings. The inspectors reviewed the Criterion 2 (NSR equipment potentially affecting LR in-
scope equipment) related to these systems and concluded the identification and resolution of
Criterion 2 equipment was acceptable. The inspectors concluded that the applicant had
performed scoping and screening for this system in accordance with the LRA and the Rule.
17. Post Accident Sampling
The Post Accident Sampling System provides a means to remotely collect, analyze, and dilute,
reactor coolant and containment atmosphere samples. The only component within the LR scope
is the sample heat exchanger which is cooled by the Component Cooling System and is included
in application Table 2.3-9 as an in-scope component in that system. The inspectors reviewed the
system scoping and screening documents, design basis information, applicable UFSAR sections
and the boundary drawings. The inspectors concluded that the applicant had performed scoping
and screening for this system in accordance with the LRA and the Rule.
18. Heating, Ventilation, and Air Conditioning (HVAC) - Auxiliary Building
This system provides heat removal of equipment spaces to ensure proper operation of safety
related equipment in the Auxiliary Building. The system components included in the scope of LR
and requiring aging management review are identified in Table 2.3-18 of the application. The
inspectors reviewed the system scoping and screening documents, design basis information,
applicable UFSAR sections and the boundary drawings. The inspectors concluded that the
applicant had performed scoping and screening for this system in accordance with the LRA and
the Rule.
19. HVAC - Containment Building (Containment Air Re-circulation Cooling System)
This system functions as an independent back up for the Containment Spray System to limit the
temperature and pressure that could be experienced in containment following a loss-of-coolant or
steam line break event to less than the design values. Heat removed by the system is
transferred to the Service Water System via four air handling unit heat exchangers. The system
components included in the scope of LR and requiring aging management review are identified in
Table 2.3-5 of the Application. The inspectors reviewed the system scoping and screening
documents, design basis information, applicable UFSAR sections and the boundary drawings.
The inspectors concluded that the applicant had performed scoping and screening for this system
in accordance with the LRA and the Rule.
8
20. HVAC - Control Room Area
This system provides heating, ventilation, cooling, filtration, air intake and exhaust isolation during
normal operation and following a design basis event. The system consists of an environmental
control system and an air clean up system. The system components included in the scope of LR
and requiring aging management review are identified in Table 2.3-19 of the application. The
inspectors reviewed the system scoping and screening documents, design basis information,
applicable UFSAR sections and the boundary drawings. The inspectors concluded that the
applicant had performed scoping and screening for this system in accordance with the LRA and
the Rule.
21. HVAC - Fuel Handling Building
This system provides ventilation and heat removal for the fuel handling building and filters
exhaust air from the building. The system components included in the scope of LR and requiring
aging management review are identified in Table 2.3-20 of the Application. The inspectors
reviewed the system scoping and screening documents, design basis information, applicable
UFSAR sections and the boundary drawings. The inspectors concluded that the applicant had
performed scoping and screening for this system in accordance with the LRA and the Rule.
22. Emergency Diesel Generator Room CARDOX System
This system is a high pressure carbon dioxide fire suppression system to extinguish a fire in the
diesel generator rooms. The system is automatically actuated from heat sensors located in the
rooms and is supplied from nineteen 75-pound CO2 cylinders located outside the room. The
system components included in the scope of LR and requiring aging management review are
identified in Table 2.3-21 of the application. The inspectors reviewed the system scoping and
screening documents, design basis information, and applicable UFSAR sections and observed
the material condition of the equipment in the plant. The inspectors concluded that the applicant
had performed scoping and screening for this system in accordance with the LRA and the Rule.
23. HVAC - Radwaste Facility
This system provides ventilation and heating for the radwaste facility The inspectors reviewed the
system description in the UFSAR, flow diagrams, and discussed the system function with the
applicant staff. There were no functions of the system that met the criteria for LR scoping. The
inspectors concluded that there was adequate basis for exclusion of this system from the LR
scope.
24. HVAC - Turbine Building
This system provides air conditioned and filtered air to the enclosed utility spaces under the
turbine concrete pedestal including the RCA access area which is located in the turbine building.
The inspectors reviewed the system description in the UFSAR, flow diagrams, and discussed the
system function with the applicant staff. The inspectors concluded that there was adequate basis
for exclusion of this system from the LR scope.
B. Evaluation of Scoping and Screening of Electrical Systems
The inspectors observed that the scoping and screening of electrical systems employed
significantly different methods than the mechanical or structural disciplines. During this
9
inspection the inspectors reviewed an Engineering Evaluation report RNP-L/LR-0120, Rev. 3,
3/12/03, Electrical Component Screening for License Renewal for H.B. Robinson - Unit 2. The
procedure described how the applicant accomplished scoping and screening of electrical
commodities to determine those needing an aging management review.
The method used to determine which electrical and I&C components are subject to an aging
management review was organized based on component commodity groups. The primary
difference in this method versus the one used for mechanical systems and structures is the order
in which the component scoping and screening steps are performed. This method was selected
for use with the electrical and I&C components since most electrical and I&C components are
active, thus, the applicant concluded that this method provided the most efficient means for
determining electrical and I&C components that require an aging management review. The
method is consistent with the industry guidance documented in NEI 95-10.
Electrical/I&C component commodity groups associated with electrical, I&C, and mechanical
systems within the scope of license renewal were identified. This step included a complete
review of design drawings and electrical/I&C component commodity groups in the plant
component database. A description and function for each of the electrical/I&C component
commodity groups were identified. The electrical/I&C component commodity groups that perform
an intended function without moving parts or without a change in configuration or properties
[screening criterion of 10 CFR 54.21(a)(1)(i)] were identified. For the resulting passive
electrical/I&C component commodity groups, component commodity groups that are not subject
to replacement based on a qualified life or specified time period [screening criterion of 10 CFR 54.21(a)(1)(ii)] were identified as requiring an aging management review. Electrical and I&C
component commodity groups included in the 10 CFR 50.49 Environmental Qualification (EQ)
Program were considered to be subject to replacement based on qualified life, and thus
eliminated from the list. Next certain passive, long-lived electrical/I&C component commodity
groups that do not support license renewal system intended functions were eliminated. Finally
the in-scope equipment identified as requiring an aging management review were compared to
the NRCs Generic Aging Lessons Learned report to ensure that differences are valid and
justified. The resulting list of electrical and I&C component commodity groups subject to an aging
management review was:
1) Bus Duct - Isolated Phase (Iso-Phase), Non- segregated 4.16 KV and 480 V bus duct
2) Non-EQ Electrical / I&C penetration Assemblies - 28 total - all manufactured by Crouse-Hinds.
3) Non-EQ Insulated Cables and Connectors - All plant systems and structures - includes splices,
fuse blocks, connectors and terminal blocks.
4) Passive Electrical Switchyard Commodities - Credited for restoration of offsite power when
recovering from an SBO event - includes iso-phase bus duct, non-segregate 480 V bus duct, high
voltage insulators, switchyard bus, and transmission conductors. The inspectors found the
methodology and the conclusions reached by the applicant to be satisfactory.
In a response to an NRC RAI concerning recovery from Station Blackout (SBO), the applicant
stated that consistent with the NRC position, the additional structural components included in the
scope of license renewal as meeting the scoping criteria of 10 CFR 54.4(a)(3) for restoration of
offsite power are as follows:
Building 175: Switchyard Relay Building
10
Isolated phase bus duct yard support structures
Switchyard and transformer structures
4 KV non-segregated bus duct yard support
The inspector found that the proposed response to RAI 2.5.2-1 regarding fuse holders needed
clarification and enhancement to reflect information contained in the applicants Calculation No.
RNP-L/LR-0390, Attachment S, Evaluation of fuse holders, Revision 1.
C. Evaluation of Scoping and Screening of Structural Components
1. Reactor Containment Building
The Reactor Containment Building is a seismic class I structures with a steel lined concrete
vertical cylinder, a hemispherical dome, and a flat base mat which is supported on piles. The
Reactor Containment Building houses the reactor vessel, reactor coolant system, and other
safety related systems. The entire building was concluded to be within the scope of license
renewal. Procedure EGR-NGGC-0502, System/Structure Scoping for License Renewal,
describes the scoping process. Calculation RPN-L/LR-0007, System/Structure Scoping for
License Renewal, performs the actual scoping for all systems and structures. Attachments to
Calculation RPN-L/LR-007 are called System/Structure Scoping Worksheets which list the
scoping results for all systems and structures. Attachment 166 lists the scoping results of the
Reactor Containment Building.
Calculation RPN-L/LR-0104, License Renewal Screening - Containment Structure Internal and
External Structural Components, addresses the screening of the Reactor Containment Structure,
Internal Structural Components, and the External Structural Components. Procedure EGR-
NGGC-0506, Civil/Structural Screening and Aging Management Review for License Renewal,
describes the screening process. Attachment 1 to Calculation RPN-L/LR-0104 addresses the
detailed screening of the commodities, namely the concrete, the steel, the pipe piles, the steel
liner, the penetration assemblies, post tension system, liner insulation, cathodic protection
system, and component supports. Attachments 1.1 and 1.2 list the components and structural
commodity screening matrix, respectively. Only active and components or structures without a
safety intended function are screened out. The inspectors agreed with this assessment.
2. Switchyard Relay Building, Switchyard and Transformer Structures
The Switchyard and Transformers together with the Switchyard Relay building were originally
assessed to not be within the scope of license renewal by the applicant as contained in Table 2.2-
2 of the LRA. In response to RAI 2.5.1-1, the applicant, due to SBO considerations, determined
that these structures are within the scope of license renewal.
11
Attachments 145 and 146 to Calculation RPN-L/LR-0007 list the scoping results of the Switchyard
Relay Building and the Switchyard and Transformer Structures, respectively. The Switchyard
Relay Building is a prefabricated metal building with doors supported on a concrete slab. The
Switchyard and Transformer Structures include those which support electrical equipment in the
Switchyard and Transformer System. Civil structures include the concrete foundations and
supporting steel structures for all electrical equipment, towers, poles, and the switchyard cable
trenches. In addition, underground electrical conduit and yard electrical panels are also included.
Attachment 32 to Calculation RPN-L/LR-0103, License Renewal Screening - Structures and
Structural Components, describes that the Switchyard and Transformer Structures are outside of
the plant but relied upon for restoration of offsite power to support SBO. The electrical equipment
includes part of the 230KV and 115KV switchyards, the overhead lines to the plant, the main,
start-up and unit auxiliary transformers. The civil/structural components include the concrete
foundations to all the electrical equipment and the steel supports. Attachment 32.2 lists the
structure commodity screening matrix.
Attachment 34 to Calculation RPN-L/LR-0103 describes the Switchyard Relay Building which
houses and supports the batteries which provide 125V DC to equipment in the switchyard.
Figure 34.1 depicts the locations of the structure and Attachment 34.2 lists the structure
commodity screening matrix for the Switchyard Relay Building. The inspectors concurred with
the assessment. The inspectors walked down the in scope portion of the switchyard structures
and structural components and found they are in good material condition.
3. Reactor Auxiliary Building
The Reactor Auxiliary Building (RAB) is a reinforced concrete seismic class I structure supported
on a piling foundation. It includes the control room, and the diesel generator room. The RAB
also includes the RHR room, the radiation monitor room, and the waste evaporation enclosure.
Attachment 211 of Calculation RPN-L/LR-0007 describes that the RAB has several intended
safety functions and the entire building is within the scope of license renewal.
Attachment 01 of Calculation RPN-L/LR-0103 contains the screening process and results. The
structural components screening matrix are listed in Attachment 1.1 and the structural commodity
screening matrix appears in Attachment 1.2. Figure 1.1 through 1.4 depict the evaluation
boundary of the RAB. The process screened out the station C battery enclosure, the elevator
on the east side of the RAB, and the external stairways as not requiring an aging management
review. The inspectors agreed with this decision.
4. Pipe Restraint Tower
Attachment 208 of Calculation RPN-L/LR-0007 describes the Pipe Restraint Tower as a structural
steel frame supported by a reinforced concrete foundation. It provides access to components
and pipe whip restraint in case of a high energy line break outside the containment for the main
steam and feedwater lines. The Pipe Restraint Tower supports the main steam safety relief and
12
isolation valves and the feedwater isolation valves. The applicant determined that the entire Pipe
Restraint Tower is within the scope of license renewal. The only commodities screened out are
stairs and ladders, jet impingement barriers, and snubbers. The inspectors concurred with this
assessment.
5. Plant Vent Stack
Attachment 224 of Calculation RPN-L/LR-0007 briefly describes that the plant Vent Stack is a 4-
6" diameter ventilation stack located at east quadrant of the Reactor Containment Building. The
stack is supported on the Reactor Auxiliary Building roof and braced from the Reactor
Containment Building by a structural steel frame at a higher elevation. Drawing CAR-2767G-211
depicts that the stack is made of 3/16" carbon steel (A36) and there is no safety related
equipment located in the proximity of the stack. The failure of the stack will not damage any
safety related structure or component. The stack itself is non-safety related and does not
perform any license renewal intended function. The applicant correctly assesses that the Plant
Vent Stack is not within the scope of license renewal. The inspectors walked down the vicinity of
the Plant Vent Stack and agreed with the applicants assessment.
6. Intake Structure
The Robinson Intake Structure is a seismic class I reinforced concrete structure. The structure
consists of three separate bays and supports four safety related service water pumps, three non-
safety related circulating water pumps, and three non-safety related fire pumps. There are three
traveling screens in each bay to remove debris from the intake water. Stop logs, fine, and rough
screens (trash racks) were designed but never were installed due to the cleanliness of the lake
water. The lake water is acid in nature with average pH values varied from 4.6 to 6.4 (measured
from 1985 to 1999) which makes it difficult to grow vegetation. The applicant assesses the Intake
Structure, in Attachment 132 of Calculation RPN-L/LR-0007, to be within the scope of license
renewal due to the fact that the structure performs several license renewal intended safety
functions. In Attachment 4.2 of Calculation RPN-L/LR-0103, the applicant only screens out a few
commodities that do not have to perform an intended safety function. The inspectors concurred
in the assessment. The inspectors walked down the Intake Structure. Most of the structure is
underwater. The above water portion of the structure looked very clean and is in good condition.
7. East Personnel Access Portal
The East Personnel Access Portal was used during construction. After the West Personnel
Access Portal was established, the East Personnel Access Portal was closed and abandoned.
The applicant determined that the East Personnel Access Portal is not within the scope of license
renewal. The inspectors agreed with the assessment.
13
8. West Personnel Access Portal
The West Personnel Access Portal is a prefabricated metal structure with a reinforced concrete
foundation. The West Personnel Access Portal is assessed to be within the scope of license
renewal because it houses and supports electrical equipment which controls and operates the
security lighting. A portion of the security lighting is credited for a fire protection function.
Therefore, the entire structure is in scope and nothing is being screened out within the evaluation
boundary of the structure. The inspectors concurred with this determination.
9. Security Emergency Diesel Generator Building
The Security Emergency Diesel Generator Building is a steel and concrete block structure on a
reinforced concrete foundation. This structure was scoped into the rule for fire protection
because the applicant received from the NRC an exemption from using 8-hour battery lighting
based on the use of security lighting. The security lighting is backed by the security diesel
generator, therefore the entire security lighting system and its supports are all within the scope of
license renewal. Attachment 12.2 of Calculation RPN-L/LR-0103 lists the structural commodities
that require an aging management review. The inspectors concurred with this decision.
10. Fuel Handling Building
The Fuel Handling Building (FHB) is comprised of three adjacent buildings and a super structure,
which supports the spent fuel cask handling machine. The three buildings are the Spent Fuel Pit
Heat Exchanger Room, the Hot Machine Shop, and the Fuel Handling Building, The FHB
performs many license renewal intended functions such as shelter and support for safety related
and non-safety related systems and components. The entire FHB is concluded to be within the
scope of license renewal. The only commodities being screened out are facilities associated with
the new fuel handling and storage and active components as listed in Attachment 3.2 of
Calculation RPN-L/LR-0103. The inspectors agreed with this assessment.
11. Electrical Manholes and Duct Banks
This group includes all yard electrical manholes and duct banks. Only three electrical manholes
are scoped into the rule. They are manholes #35 and #36 and an unnumbered electrical
manhole located west of the Unit 1 Administration Building. There are two manholes at the
Intake Structure and they are considered as part of the Intake Structure. Electrical manholes and
duct banks associated with the security lighting system are scoped and screened separately.
The cables from manholes 35 and 36 are buried directly without duct banks. The manhole are
constructed with reinforced concrete. Commodities associated with these three manholes all
require aging management review. There are no duct banks associated with these structures.
The inspectors concurred with this assessment.
14
12. Reservoir and Dam
The reservoir (Lake Robinson) is a 2200-acre impoundment which provides plant cooling for
normal and emergency situations. It also supplies water for fire protection and is the ultimate
heat sink for the plant. The earth dam has a vertical clay core and supporting shell of compacted
sand. Rip rap protection is provided on the upstream side. There are a spillway, gates, and
valves provided for down stream water release. The applicant determined that the dam and
reservoir are within the scope of license renewal. Figure 13.1 of Attachment 13 to Calculation
RPN-L/LR-0103 depicts the evaluation boundary of the dam and reservoir and Attachment 13.2
lists all the structural commodities that require aging management review. The inspectors
concurred with this determination.
13. Tech Support Center/Emergency Operations Facility (TSC/EOF)
The TSC/EOF Training Building is a reinforced concrete structure used for training, offices, and is
an emergency management facility during plant accidents but does not perform any license
renewal intended safety functions. The applicant assessed that the TSC/EOF is not within the
scope of license renewal. The inspectors agreed with this assessment.
14. Concrete Trenches
This structure is the reinforced concrete trench between the Turbine Building and the Condensate
Storage Tank. The trench continues inside the Turbine Building concrete floor slab and this
portion of the trench is reviewed together with the Turbine Building. The trench is within the
scope of license renewal because it supports and protects safety related and non-safety related
equipment. Figure 24.1 of Attachment 24 to Calculation RPN-L/LR-0103 shows the structure
evaluation boundary. The inspectors concurred with the applicants decision.
15. Tank Foundations
The foundations of the safety related Condensate Storage Tank (CST) and the Refueling Water
Storage Tank (RWST) are reinforced concrete ring structures with a thickness of 3'-6" and a
depth of 5'-0" as they are described in Attachments 128 and 126 of Calculation RPN-L/LR-0007,
respectively. The applicant assessed that the tank foundations are within the scope of license
renewal because they provide structural support to safety related equipment. The evaluation
boundary for the CST foundation is shown in Figure 16.1 0f Attachment 16 to Calculation RPN-
L/LR-0103 and for the RWST foundation is in Figure 15.1 of Attachment 15. The screening
results are listed in Attachments 16.2 and 15.2 of Calc. RPN-L/LR-0103 for the CST and RWST
foundations, respectively. The inspectors walked down the CST foundation and found that the
structure is in good material condition. The inspectors found that the applicants assessment
was acceptable.
15
D. Evaluation of Scoping and Screening of Fire Protection Systems
Fire protection features and commitments are described in detail in the Robinson UFSAR. The
systems and structures at Robinson that support either fire protection design or safe shutdown
following a fire are considered within the scope of license renewal. Those items providing fire
suppression, fire detection, and electrical power supply to that equipment are classified Quality
class B-03 in the EDB. So any system with components classified as B-03 was considered in
scope. Also, safe shutdown components credited in analyses to comply with 10 CFR 50,
Appendix R, are included in the Appendix R Component Database. This database was also used
to identify systems in scope for license renewal. In addition, structures credited in the definition
of fire areas and zones were considered in scope.
The inspectors examined boundary diagrams which show the evaluation boundaries for the
portions of fire protection systems that the applicant concluded are within the scope of license
renewal. The inspectors found no significant discrepancies in the fire protection equipment
highlighted as being in LR scope on the boundary drawings. The inspectors did observe that the
fire protection boundary drawings HBR2-8255LR series sheets 1 through 6 contained a minor
error. The reference to the fire protection screening calculation should have been RNP-L/LR-
0139 instead of RNP-L/LR-0129 which appears on the drawings. The applicant included this
issue in AR 89349 for corrective action.
E. Visual Observations of Plant Equipment in Containment
NRC performed visual inspections of the interior of the Robinson containment on October 24,
2002 during a refueling outage. This included observation of accessible portions of plant SSCs
and electrical cable inside the containment to observe material condition and inspect for aging
conditions that might not have been previously recognized and addressed in the LRA. The
following is a partial list of equipment observed:
FW system piping
personnel and equipment hatches
SGs B and C, including supports
ventilation ducting
electrical cable
B and C reactor coolant pump cubicles/loop rooms
reactor coolant system piping
CC system piping and valves
containment electrical penetrations
excess letdown heat exchanger
16
reactor vessel head
reactor coolant drain collection tank and piping
pressurizer relief tank
pressurizer surge line and whip restraint
containment pipe penetration area
containment sump area
containment HVAC units
The observations of general material conditions included: inspection of piping components for
evidence of leaks or corrosion, inspection of coatings (piping, tanks, and structural components),
and inspection of electrical cable for indications of deterioration. The material condition of the
Robinson containment was good and no significant aging management issues were identified.
The inspectors could not inspect the steel containment liner due to the unique design of the
Robinson containment. Specifically most of the liner is covered by insulation panels.
Exit Meeting Summary
The results of this inspection were discussed on April 4, 2003, with members of the CPL staff in
an exit meeting open for public observation at the Hartsville Memorial Library. The applicant
acknowledged the findings presented and presented no dissenting comments.
17
ATTACHMENT 1
SUPPLEMENTAL INFORMATION
PARTIAL LIST OF PERSONS CONTACTED
Applicant
C. Baucom, Supervisor Licensing
C. Burton, Director Site Operations
T. Cleary, Plant General Manager
T. Clements, Manager Licens Renewal
M. Heath, Supervisor License Renewal
D. McNeill, Supervisor Communications
J. Fletcher, Manager Nuclear Support Services
J. Moyer, Robinson Site Vice President
R. Stewart, Supervisor License Renewal
S. Tally, Mechanical Engineer
NRC
C. Casto, Director Division of Reactor Safety
M. Cora, Project Manager
B. Desai, Senior Resident Inspector
D. Jones, Resident Inspector
S. Mitra, Project Manager
Public
M. Gandy, South Carolina Department of Health
and Environmental Control
LIST OF DOCUMENTS REVIEWED
License Renewal Boundary Drawings
5379-1971LR, Reactor Coolant System Flow Diagram, Sheet 1 Rev. 0, Sheet 2 Rev. 1
18
HBR2-9067LR, Reactor Vessel Level Indicator Switches Flow Diagram, Rev. 0
G-190204CLR, Chemical Feed System Flow Diagram, Rev. 1
G-190234LR, Steam Generator Blowdown and Wet Layup System Flow Diagram, Rev. 1
5379-685LR, Chemical and Volume Control System Purification and Make-Up Flow Diagram,
Sheets 1 & 2 Rev. 1
5379-1485LR, Spent Fuel Pit Cooling System Flow Diagram, Rev. 1
5379-1484LR, Residual Heat Removal System Flow Diagram, Rev. 1
HBR2-8606LR, Sheet 2, Nitrogen Supply System Flow Diagram, Rev. 15
HBR-7063LR, Sheet 1, Flow Diagram Legend, Rev. 13
HBR2-6490LR, Sheet 1, Containment Vapor and Pressure Sampling System Flow Diagram, Rev.
13
G-190199LR, Sheet 1, Service & Cooling Water System Flow Diagram, Rev. 63
G-190199LR, Sheet 2, Service & Cooling Water System Flow Diagram, Rev. 62
5379-376LR, Sheet 1, Component Cooling Water system Flow Diagram, Rev. 34
5379-376LR, Sheet 3, Component Cooling Water system Flow Diagram, Rev. 22
5379-376LR, Sheet 4, Component Cooling Water system Flow Diagram, Rev. 31
G-190261LR, Sheet 1, Penetration Pressurization Flow Diagram, Rev. 26
G-190261LR, Sheet 4, Penetration Pressurization Flow Diagram, Rev. 31
G-190304LR, HVAC - Turb. Fuel , Aux., Reactor & Radwaste Bldgs., sheets 1, 2, 3 & 4, Rev. 1
G-190197LR, Feedwater, Condensate & Air Evacuation System Flow Diagram, sheets 1,3, & 4,
Rev. 1
G-190202LR, Primary & Make-Up Water System Flow Diagram, sheet 3 0f 7, Rev. 0
HBR2-6933LR, Post Accident containment Venting and H2 Recombiner System Flow Diagram,
Rev. 1
5379-920LR, Liquid Waste Disposal System Flow Diagram, sheet 3 of 8, Rev. 0
G-190200LR, Instrument and Station Air System Flow Diagram, sheets 2,3, 5,and 9, Rev. 1
5379-353LR, Primary Sampling System Flow Diagram, Rev. 1
HBR2-8261LR, Post Accident Sample Station Flow Diagram, sheet 1 of 2, Rev. 1
G-190204ALR, Emergency Diesel Generator System Flow Diagram, Sh. 1-3, Rev. 1
G-190204DLR, Fuel Oil System Flow Diagram, Sh. 1-3, Rev. 2, 1, 1
5379-1082LR, Safety Injection System Flow Diagram, Sh. 1-5, Rev. 1, 2, 1, 0, 0
HBR2-8679LR, Dedicated Shutdown Emergency Diesel Generator System Flow Diagram, Sh. 1-
2, Rev. 1, 1
HBR2-8255LR, Fire Protection System, Sh. 1-6
19
Plant Drawings
HBR2-11390, Appendix R and Station Blackout Safe-Shutdown Analysis Flowpath/Boundary
Diagram, Sheet 1 Rev. 3 and Sheet 3 and 12 Rev. 2
A-190301, Sheet 3A (TYP), Main Steam Isolation Valve V1-3A, Rev. 6
HBR2-10618, Sheets 141, 142, Inservice Inspection Drawing Component Coolant System, Rev 3
G-190190, General arrangement Reactor Auxiliary Building - Plans, Rev. 23
G-190272, Reactor Component Cooling Water System Piping Plan, Rev. 11
CAR-2762G-211, Reactor Auxiliary Building Vent Stack Modification, Rev 0
HBR2-9800, Plot Plan, Rev 7
License Renewal Calculations
RNP-L/LR-0003, Fire Protection System/Structure Scoping for License Renewal, Rev. 1
RNP-L/LR-0004, Station Blackout (SBO) System/Structure Scoping for License Renewal, Rev. 3
RNP-L/LR-0006, Non-Safety-Related Equipment Affecting Safety-Related Equipment - License
Renewal System/Structure Scoping, Rev. 2
RNP-L/LR-0007, System/Structure Scoping for License Renewal, Rev. 3
RNP-L/LR-0396, Screening and Aging Management Review Criterion 2 Piping, Rev. 2
RNP-L/LR-0144, System Screening-Reactor Coolant System, Rev. 1
RNP-L/LR-0154, System Screening-Reactor Vessel and Internals, Rev. 0
RNP-L/LR-0153, System Screening-Reactor Vessel Level Indicator Switches, Rev. 0
RNP-L/LR-0155, System Screening-Steam Generator, Rev. 0
RNP-L/LR-0138, System Screening-Steam Generator Blowdown System, Rev. 1
RNP-L/LR-0130, System Screening-Chemical and Volume Control System, Rev. 2
RNP-L/LR-0105, System Screening-Spent Fuel Pool Cooling System, Rev. 0
RNP-L/LR-0112, System Screening-Residual Heat Removal System, Rev. 0
RNP-L/LR-0113, System Screening - Safety Injection System, Rev. 2
RNP-L/LR-0116, System Screening - Diesel Generator System, Rev. 1
RNP-L/LR-0115, System Screening - Dedicated Shutdown Diesel System
RNP-L/LR-0117, System Screening - Fuel Oil System, Rev. 1
RNP-L/LR-0143, System Screening - EOF/TSC Security Emergency Diesel Generator, Rev. 0
RNP-L/LR-0121, License Renewal Mechanical Systems Evaluation Boundaries, Rev. 5
RNP-L/LR-0107, Instrument Air System Screening Calculation, Rev. 0
RNP-L/LR-0132, Component Cooling Water System Screening Calculation, Rev. 2
20
RNP-L/LR-0137, Service Water System Screening Calculation, Rev. 0
RNP-L/LR-0145, System Screening - Containment Pressure Relief System, Rev. 1
RNP-L/LR-0146, Containment Vacuum Breaker System Screening Calculation, Rev. 0
RNP-L/LR-0148, System Screening - Containment Purge System, Rev. 0
RNP-L/LR-0136, System Screening - Primary and Demineralized Water Make-up System, Rev. 1
RNP-L/LR-0129, System Screening - AFW System, Rev. 2
RNP-L/LR-0126, System Screening - Post Accident Sampling System, Rev. 0
RNP-L/LR-0128, System Screening - Primary Sampling System, Rev. 1
RNP-L/LR-0140, System Screening - EDG CARDOX System, Rev. 1
RPN-L/LR-0124, License Renewal - Identification of Civil Commodity Types and Bulk Screening
Criteria, Rev. 3
RPN-L/LR-0103, License Renewal Screening - Structures and Structural Components, Rev. 2
RPN-L/LR-0104, License Renewal Screening - Containment, Rev. 1
RNP-L/LR-0120, Electrical Component Screening for License Renewal for H.B. Robinson - Unit
2 Rev. 3
RNP-L/LR-0390, Evaluation of fuse holders, Rev. 1
License Renewal Procedures
EGR-NGGC-0501, Nuclear Plant License Renewal Program, Rev. 5
EGR-NGGC-0502, System/Structure Scoping for License Renewal, Rev. 3
EGR-NGGC-0503, Mechanical Component Screening for License Renewal, Rev. 5
EGR-NGGC-0506, Civil/Structural Screening and Aging Management Review for License
Renewal, Rev. 3
System Descriptions
SD-002, Safety Injection System, Rev. 10
SD-005, Emergency Diesel Generators, Rev. 7
SD-056, Dedicated Shutdown System and TSC/EOF/PAP Diesel Generator System, Rev. 2
DBD/R87038/SD32, Design Base Document - Auxiliary Feedwater System, Rev. 6
SD-043, System Description - Diesel Generator Fire Suppression System, Rev.1
SD-015, System Description - Sampling System, Rev. 4
SD-019, System Description - Radiation Monitoring System Rev. 4
DBD/R87038/SD36. Design Base Document - Post Accident HVAC Systems, Rev. 6
21
SD-023, Waste Disposal System, Rev. 3
SD-037, Containment HVAC, Rev.5
Plant Procedures
OP-909, Fuel Oil System, Rev. 30
Support References
Robinson Nuclear Plant License Renewal Application, 6/17/02
H. B. Robinson Updated Final Safety Analysis Report
Technical Specifications Bases Section B 3.8.3, Diesel Fuel Oil and Starting Air
Generic Interface Document GID/90-181/00/RCI, Appendix A Individual Pentration Evaluations,
Revision 2
22
ATTACHMENT 2
H. B. Robinson
LICENSE RENEWAL INSPECTION PLAN
LICENSE RENEWAL SCOPING RESULTS
FOR MECHANICAL SYSTEMS
System Name
System in License
Renewal Scope?
Yes
Chemical and Volume Control System
Yes
Component/Closed Cooling Water System
Yes
Containment Pressure Relief System (CVPRS)
Yes
Containment Purge System (CV PUR)
Yes
Yes
Containment Vacuum Breaker System (CV VBS)
Yes
Containment Vapor and Pressure Sampling System
Yes
Dedicated Shutdown Diesel Generator (DSD)
Yes
Diesel Generator System (DIESEL)
Yes
Emergency Diesel Generator Car Dox System (CARDOX)
Yes
EOF/TSC Security Emergency Diesel Gen. (EOF DG)
Yes
Fire Protection CO2 System (CO2)
Yes
Fuel Oil System (FO)
Yes
Halon Supply System (HALON)
Yes
HVAC Auxiliary Building (HVAC)
Yes
HVAC Containment Building System (HVAC)
Yes
Yes
HVAC Fuel Handling Building (HVAC)
Yes
No
No
Instrument Air System (IA)
Yes
Isolation Valve Seal Water System (IVSW)
Yes
Liquid Waste Processing System (WDS)
Yes
23
Post Accident Hydrogen System
Yes
Post Accident Sampling System
Yes
Process/Area Radiation Monitoring System (RMS)
Yes
Yes
Reactor Vessel and Internals System
Yes
Residual Heat Removal System (RHR)
Yes
Rx Vessel Level Instrumentation / ICCM System
Yes
Safety Injection System
Yes
Service Water System (SW)
Yes
Site Fire Protection System (SFPS)
Yes
Spent Fuel Pool Cooling System (SFPCS)
Yes
Yes
24
H. B. Robinson
LICENSE RENEWAL INSPECTION PLAN
LICENSE RENEWAL SCOPING RESULTS
FOR STRUCTURES
Structure Name
Structure in License
Renewal Scope?
Bldg 175: Switchyard Relay Building
No
Bldg 200: Reactor Containment Building
Yes
Bldg 205: Reactor Auxiliary Building
Yes
Bldg 300: West Personnel Access Portal (PAP)
Yes
Bldg 310: EOF/TSC Security Emergency Diesel
Generator Building
Yes
Bldg 355: East Personnel Access Portal (PAP)
No
Bldg 410: Tech Support Center/Emergency Operations
Facility (TSC/EOF)
No
Bldg N/A: Intake Structure
Yes
Bldg N/A: Plant Vent Stack
No
Bldg 215, 220, and 225: Fuel Handling Building
Yes
Concrete Trenches
Yes
Electrical Manholes and Duct Banks
Yes
Pipe Restraint Tower
Yes
Reservoir and Dam
Yes
Switchyard and Transformers
No
Tank Foundation: Condensate Storage
Yes
Tank Foundation: Refueling Water Storage Tank
Yes
25
H. B. Robinson
LICENSE RENEWAL INSPECTION PLAN
LICENSE RENEWAL SCOPING RESULTS FOR
ELECTRICAL/I&C SYSTEMS
System Name
System in License
Renewal Scope?
125 V DC Battery/Charger/Distribution System
Yes
208/120 VAC Distribution System
Yes
4 KV AC Distribution System (4KV)
Yes
480 V AC Distribution System (480 VAC)
Yes
Dedicated Shutdown System (DSS)
Yes
Emergency Communications System
No
FCC Licensed Portable Radios (P RAD)
Yes
Fire Alarm Console Computer (FAC)
Yes
Post Accident Monitoring System
Yes
Site Fire Detection System (SFDS)
Yes
Site Grounding System (S GND)
No
Switchyard and Transformer System (SWTR)
No
26
ATTACHMENT 3
LIST OF ACRONYMS USED
Alternating Current
Auxiliary Feedwater System
Aging Management Review
Action Request
Component Cooling Water System
Carolina Power and Light Company
Containment Spray System
Condensate Storage Tank
Chemical and Volume Control System
Diesel Generator
DSDG
Dedicated Shutdown Diesel Generator
Emergency Core Cooling Systems
Equipment Data Base
Environmental Qualification Program
FHB
Fuel Handling Building
Fuel Oil System
Feedwater System
Heating Ventilation and Air Conditioning
Instrument Air
ICCM
Inadequate Core Cooling Monitor System
LR
Non Safety Related
NRC Office of Nuclear Reactor Regulation
Reactor Auxiliary Building
Request for Additional Information
RV
Reactor Vessel
Refueling Water Storage Tank
Station Blackout Event
27
SFPC
Spent Fuel Pool Cooling System
Service Air System
Safety Injection
SR
Safety Related
Systems, Structures, and Components
Service Water System