ML020850432
| ML020850432 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 03/25/2002 |
| From: | Lanksbury R NRC/RGN-III/DRP/RPB5 |
| To: | Warner M Nuclear Management Co |
| References | |
| IR-02-003 | |
| Download: ML020850432 (28) | |
See also: IR 05000266/2002003
Text
March 25, 2002
Mr. M. Warner
Site Vice President
Kewaunee and Point Beach Nuclear Plants
Nuclear Management Company, LLC
6610 Nuclear Road
Two Rivers, WI 54241
SUBJECT:
POINT BEACH NUCLEAR PLANT
NRC INSPECTION REPORT 50-266/02-03(DRP); 50-301/02-03(DRP)
Dear Mr. Warner:
On February 25, 2002, the NRC completed a team inspection at the Point Beach Nuclear Plant.
The enclosed report documents the inspection findings which were discussed on February 25
with you and members of your staff.
This inspection was an examination of activities conducted under your license as they relate to
the identification and resolution of problems, and compliance with the Commissions rules and
regulations and with the conditions of your operating license. Within these areas, the
inspection involved selected examination of procedures and representative records,
observations of activities, and interviews with personnel.
On the basis of the samples selected for review, the team concluded that, overall, problems
were properly identified, evaluated, and resolved within the problem identification and resolution
program. However, the inspectors identified one finding for which the safety significance was
still to be determined. This issue pertained to the failure of the 2P-15B safety injection pump on
February 20, 2002, because of nitrogen gas binding. The conditions that resulted in the
accumulation of nitrogen in the pump were still being evaluated by both your staff and the NRC
at the end of this inspection. This issue will be considered an Unresolved Item pending
completion of those reviews. A preliminary NRC review of the risk significance of the finding
determined that it was at least of very low safety significance (Green).
M. Warner
-2-
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 System (PARS) component of
NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at
http://www.nrc.gov/NRC/ADAMS/index.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Roger Lanksbury, Chief
Branch 5
Division of Reactor Projects
Docket Nos. 50-266; 50-301
Enclosure:
Inspection Report 50-266/02-03(DRP);
50-301/02-03(DRP)
cc w/encl:
R. Grigg, President and Chief
Operating Officer, WEPCo
R. Anderson, Executive Vice President
and Chief Nuclear Officer
T. Webb, Licensing Manager
D. Weaver, Nuclear Asset Manager
T. Taylor, Plant Manager
A. Cayia, Site Director
J. ONeill, Jr., Shaw, Pittman,
Potts & Trowbridge
K. Duveneck, Town Chairman
Town of Two Creeks
D. Graham, Director
Bureau of Field Operations
A. Bie, Chairperson, Wisconsin
Public Service Commission
S. Jenkins, Electric Division
Wisconsin Public Service Commission
State Liaison Officer
DOCUMENT NAME: G:\\poin\\poi2002003 drp.wpd
To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy
OFFICE
RIII
C RIII
N
NAME
MKunowski/trn
RLanksbury
DATE
03/25/02
03/25/02
OFFICIAL RECORD COPY
M. Warner
-3-
ADAMS Distribution:
WDR
BAW
RidsNrrDipmIipb
GEG
PGK1
C. Ariano (hard copy)
DRPIII
DRSIII
PLB1
JRK1
U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Docket Nos:
50-266; 50-301
License Nos:
Report No:
50-266/02-03(DRP); 50-301/02-03(DRP)
Licensee:
Nuclear Management Company, LLC
Facility:
Point Beach Nuclear Plant, Units 1 & 2
Location:
6610 Nuclear Road
Two Rivers, WI 54241
Dates:
January 22 through February 25, 2002
Inspectors:
M. Kunowski, Project Engineer (Lead Inspector)
P. Krohn, Senior Resident Inspector
R. Langstaff, Senior Reactor Engineer
Approved by:
Roger Lanksbury, Chief
Branch 5
Division of Reactor Projects
2
SUMMARY OF FINDINGS
IR 05000266-02-03; 05000301-02-03, on 1/22-2/25/2002. Nuclear Management Company,
LLC, Point Beach Nuclear Plant, baseline inspection of the identification and resolution of
problems.
The inspection was conducted by two regional inspectors and a resident inspector. No findings
were identified during this inspection. The significance of most findings is indicated by their
color (Green, White, Yellow, Red) using Inspection Manual Chapter 0609, Significance
Determination Process (SDP). Findings for which the SDP does not apply are indicated by
No Color or by the severity level of the applicable violation. The NRCs program for
overseeing the safe operation of commercial nuclear power reactors is described at its Reactor
Oversight Process website at http://www.nrc.gov/NRR/OVERSIGHT/index.html.
Identification and Resolution of Problems
The team concluded that the licensee was generally effective at identifying problems and
putting them into the corrective action program. There was strong management emphasis on
plant staff to identify problems and, overall, a very responsive plant staff. Since 1997, there
had been an average of 4120 condition reports written each year. A recent change from a
mainframe-based, dated, and user-unfriendly corrective action database to a Web-based
system was expected by the licensee to improve plant staff involvement with the corrective
action program and to increase program management capability. Corrective action program
timeliness was still an area of weakness and one where the licensee was expending additional
efforts. Included in this effort was an emphasis on making improvements for overdue or less
than prompt assessments of problems and implementation of corrective actions and for an
excessive number of due date extensions. Although there had been some dissatisfaction
expressed with some aspects of the corrective action program, the inspectors identified no
impediments to a safety conscious work environment. One finding was identified that was at
least of very low safety significance (Green). This finding pertained to the failure of the 2P-15B
safety injection pump on February 20, 2002, because of nitrogen gas binding. The conditions
that resulted in the accumulation of nitrogen in the pump were still being evaluated by both the
licensees staff and the NRC at the end of this inspection. This issue will be considered an
Unresolved Item pending completion of those reviews.
3
Report Details
4.
OTHER ACTIVITIES (OA)
4OA2 Identification and Resolution of Problems
a. Effectiveness of Problem Identification
(1) Inspection Scope
The inspectors conducted plant tours; observed surveillance tests in progress;
interviewed plant personnel; and reviewed inspection reports issued over the last year;
corrective action program documents (condition reports (CRs) - as of
December 21, 2001, CRs were replaced by documents called CAPs (Corrective Action
Program documents)), and selected maintenance work orders (WOs) for several high
risk systems to determine if problems were being properly identified, characterized, and
entered into the corrective action program for evaluation and resolution. These systems
were Service Water (SW), 4160-volt, emergency diesel generators (EDGs), safety
injection (SI), and instrument air. The inspectors also reviewed several recent licensee
audits and self-assessments. The effectiveness of the audits and assessments was
evaluated by comparing the audit and assessment results against self-revealing and
NRC-identified issues. A listing of the documents requested by the inspectors prior to
the inspection and those documents reviewed during the inspection is included at the
end of this report.
(2) Findings
In general, problems were properly identified, characterized, and entered into the
corrective action program for evaluation and resolution. There was strong management
emphasis on plant staff to document problems in the corrective action program and a
plant staff that, overall, was very responsive. Since 1997, there had been an average of
4120 CRs written per year. In 2001, there were 3819 CRs/CAPs generated. On
December 21, 2001, the licensee switched its corrective action program database
system from a mainframe-based, dated, and relatively user-unfriendly system (called
NUTRK) to a Web-based, user-friendly system (called t-Track).
Several process improvements had helped to encourage the writing of CRs\\CAPs: the
CR\\AR hotline; department corrective action program liaisons; the new web-based
system; and the Good Catch initiative for examples of notably good problem
identification. Through routine trending of corrective action program data, the licensee
had identified instances where CR/CAP generation rates by various work groups had
not met station management expectations. For instance, in one plant group, the
expected number of CRs/CAPs were being generated but more than 85% of them were
written by 2 of the 23 persons in the work group. For another group, the percentage of
self-identified CAPs fell below an expected value. In both examples, the licensee took
corrective actions.
4
Regarding audits and self-assessment findings, there were no major discrepancies with
the observations of the inspectors. Appropriate corrective actions were taken by the
licensee for problems identified during the audits and self-assessments.
b.
Prioritization and Evaluation of Issues
(1) Inspection Scope
The inspectors reviewed a sample of CRs/CAPs to verify the appropriateness of the
category assigned, operability and reportability determinations, extent of condition
evaluations, root and apparent cause evaluations, and the assigned corrective actions.
As part of this assessment, the inspectors attended the stations daily management
meeting where newly generated CRs/CAPs were reviewed and the subsequent daily
meeting of department corrective action program liaisons. The inspectors also attended
a meeting of the Corrective Action Review Board (CARB). In addition, the inspectors
reviewed licensee actions on several problems identified by the inspectors during the
previous problem identification and resolution inspection (PI&R) in March 2001 (NRC
Inspection Report 50-266/01-06; 50-301/01-06). The documents listed at the end of the
report were used by the inspectors during the assessment of this area.
(2) Findings
In general, issues were appropriately categorized, prioritized, and evaluated. In
addition, licensee actions to address a concern identified during the previous PI&R with
the appropriateness of the initial screening of CRs were generally effective. During the
review of CRs/CAPs, the inspectors identified one example (CR 01-0203, 4KV System
Grounds) where not all of the pertinent evaluations conducted by the licensee for a
problem had been documented in the closed-out CR. This example and other examples
identified by the licensee highlight the need for continued emphasis by the licensee on
thorough documentation of evaluations and corrective actions.
c. Effectiveness of Corrective Actions
(1) Inspection Scope
The inspectors reviewed CRs/CAPs to verify that corrective actions commensurate with
the issues were identified and implemented in a timely manner, including corrective
actions to address common cause or generic concerns. During the previous PI&R, the
inspectors identified concerns with daisy-chaining---the closing of CRs to other CRs
which could be closed to yet other CRs-and the possibility that not all of the corrective
actions for the various CRs would be taken because of the difficulty in tracking all of the
problems that may be closed to any one CR. In addition, the inspectors in the previous
PI&R identified a concern with corrective action program timeliness, in that several CRs
had more than a few due date extensions and several CR evaluations and corrective
actions were overdue or had exceptionally extended due dates. The documents listed
at the end of the report were used during the review.
5
(2) Findings
Generally, effective corrective actions commensurate with the issues were identified by
the licensee and implemented in a timely manner. However, problems with overdue
problem assessments and implementation of corrective actions, and with excessive
number of due date extensions were identified by the licensee and the inspectors.
Licensee corrective actions for these problems were ongoing as of the end of the
inspection. Specific observations in this area are discussed below.
The inspectors reviewed the licensees actions on CR 93-137, which was written
in 1993 and was still open at the time of the inspection. This CR was written to
document a potential problem with fault currents exceeding the breaker rating for
certain short circuits (bolted faults) in the 480-volt, 4160-volt, and 13.8-kilovolt
systems. This issue had previously been reviewed in late 1996 by the NRC and
a violation was identified for untimely corrective actions (Inspection Report
No. 50-266/96018; 50-301/96018). During the present inspection, the inspectors
concluded that continuing actions by the licensee had been timely. Through
procedure changes and extensive engineering analyses employing a reduction
of over-conservatisms, the licensee had been able to narrow down the problem
and had developed and approved a plan to upgrade certain 480-volt breakers
and bus-work over the next several years that should allow closure of
CR 93-137.
Regarding daisy-chaining, the inspectors reviewed an instance where at least
11 CRs pertaining to various problems with the commercial grade dedication and
procurement programs were ultimately closed, either directly or through other
CRs that were closed directly, to one corrective action (Action Number 23) of the
CR written to address a problem with the Alert and Notification System. The
inspectors identified that the two recommended corrective actions for
CR 00-2933, relating to the procedure for the conditional release of QA items
from receiving, had not been implemented. CR 00-2933 had been closed to
CR 00-2312, which had been closed to Action Number 23. Action Number 23
was closed on November 16, 2001. In this instance, the items not corrected
were minor.
Regarding the issue with excessive due date extensions, during the previous
PI&R, the inspectors noted that a CR written in 1997 (CR 97-0249) for the need
to revise the administrative procedure controlling the use of equivalent spare
parts in safety-related systems had the due date extended 13 times. And while
the procedure was revised early last year in response to the procurement of a
replacement service water pump motor with inadequate wire insulation, the CR
remained open pending incorporation of other planned changes to the
procedure. During this PI&R, the inspectors noted that the CRs due date had
now been extended 18 times; however, near the end of the inspection, the
procedure revision to address the remaining changes was approved.
In an issue related to timeliness of corrective actions, the inspectors noted that
CR 01-0368 dealt with an unexpected apparent rise in Unit 2 power during a
dilution on Unit 1 on Feb 2, 2001. For this CR there were two corrective actions,
6
one to do an apparent cause evaluation (ACE) and the other to make an
Operations Notebook entry to notify all crews. The due date for this last item
was initially April 26, 2001, but was changed five times before the action was
closed without being taken because so much time had elapsed since the event
and the operating crews were already aware of the event.
Another timeliness issue was associated with the failure on February 20, 2002,
of the Unit 2 B SI pump. The pump seized and failed during a monthly
preventative-maintenance lubrication activity. The licensees initial determination
was that the pump seized due to nitrogen gas binding caused by leakage of
nitrogen-saturated water from the 2A SI accumulator back through two or more
check valves. The licensee also established that corrective actions proposed
after an August 1999 review of NRC Information Notice (IN) 88-23,
Supplement 5, Potential for Gas Binding of High Pressure Safety Injection
Pumps During a Loss-of-Coolant Accident, pertaining to the potential for gas
binding of high head safety injection pumps, were not timely. Timely completion
of these actions may have prevented the failure of the pump. In addition, the
inspectors noted that the possibility of plant conditions conducive of gas binding
was identified in February 2001 when CR 01-0454 was written because of
decreasing level in the Unit 2A SI accumulator. Since much of this information
came to light at the end of the inspection, the inspectors were not able to
complete an evaluation of these issues and had not come to any enforcement
conclusion on this particular matter.
Using the Significance Determination Process (SDP) Phase 1 Screening
Worksheet and the Phase 2 Worksheets for the Mitigating Systems
Cornerstone, the inspectors concluded that enough nitrogen gas may have been
present to cause failure of the 2P-15B pump at anytime during the 30-day period
prior to the pumps failure. The pumps failure rendered one train of SI incapable
of performing its safety function. Based on this information, this finding was
considered to be at least of very low safety significance (Green). Pending
completion of a Phase 3 SDP analysis, the safety significance of the finding is
To Be Determined (TBD) and this issue is considered an Unresolved Item
(URI 50-301/02-03-01).
d. Assessment of Safety Conscious Work Environment
(1) Inspection Scope
The inspectors interviewed plant staff and CRs/CAPs to assess whether there were
impediments to the establishment of a safety conscious work environment.
(2) Findings
From the interviews and record reviews, the inspectors identified no impediments to a
safety conscious work environment. Some individuals expressed dissatisfaction with
some aspects of the corrective action process, such as the user-unfriendly NUTRK
database system (which had since been replaced by a user-friendly Web-based system)
and workers being assigned to assess and correct problems that were identified by the
7
same workers but would be more efficiently assessed and corrected by someone else.
But the inspectors noted a strong emphasis by management on establishing an
atmosphere conducive to employees readily documenting and resolving problems and
an overall strong sentiment by interviewed plant staff to document problems.
4OA6 Meeting(s)
.1
Exit Meeting
The inspectors presented the inspection results to Mr. M. Warner and other members of
licensee management in an exit meeting on February 25, 2002. Licensee management
acknowledged the findings presented and indicated that no proprietary information was
provided to the inspectors.
8
KEY POINTS OF CONTACT
Nuclear Management Company, LLC (NMC)
J. R. Anderson
Point Beach Nuclear Plant (PBNP) Production Planning Manager
L. Armstrong
Design Engineering Manager
D. Black
Nuclear Safety Analysis Senior Engineer
A. J. Cayia
Kewaunee-Point Beach (KPB) Site Director
F. Flentje
NRC Coordinator
D. Hettick
Performance Assessment Manager
R. Hopkins
Nuclear Oversight Supervisor
T. C. Kendall
Design Engineering Supervisor
P. Kleinschmidt
Bolted Fault Project Manager
C. W. Krause
Senior Regulatory Compliance Engineer
R. G. Mende
KPB Engineering Director
K. Peveler
KPB Nuclear Oversight Manager
S. A. Pfaff
Corrective Action Supervisor
R. Pulec
KPB Performance Assessment Manager
R. Repshas
KPB Support Services Manager
G. D. Strharsky
PBNP Assistant Operations Manager
T. H. Taylor
PBNP Plant Manager
M. Warner
Site Vice-President
T. J. Webb
KPB Regulatory Affairs Manager
J. Walsh
KPB Procedures Program Manager
W. Yarosz
KPB Emergency Planning Supervisor
ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
50-301/02-03-01
2P-15B Safety Injection Pump Failure During Monthly
Preventative Maintenance Lubrication Activity
Closed
None
Discussed
None
9
LIST OF ACRONYMS USED
Apparent Cause Evaluation
Action Request
American Society of Mechanical Engineers
CA
Corrective Action
Corrective Action Program
Corrective Action Review Board
CR
Condition Report
Direct Current
Emergency Operating Procedure
Engineering Work Request
Final Safety Analysis Report
Institute of Nuclear Power Operations
KPB
Kewaunee-Point Beach
KV
Kilovolt
LCO
Limiting Condition for Operation
LER
Licensee Event Report
Less Than Adequate
Motor-Operated Valve
Non-Cited Violation
Nuclear Management Company, LLC
NP
Nuclear Power Business Unit Procedure
OA
Organizational Assessment
Operating Experience
Operating Instruction
Out-Of-Service
PBNP
Point Beach Nuclear Plant
Post-Maintenance Testing
psi
Pounds Per Square Inch
Quality Assurance
QCR
Quality Condition Report
Root Cause Evaluation
Reactor Coolant Pump
Significance Determination Process
Senior Reactor Operator
TS
Technical Specification
V
Volt
LIST OF DOCUMENTS REVIEWED
The following is a list of licensee documents reviewed during the inspection. Inclusion of a
document on this list does not imply that NRC inspectors reviewed the entire document, but,
rather that selected sections or portions of the document were evaluated as part of the overall
inspection effort. In addition, inclusion of a document on this list does not imply NRC
acceptance of the document, unless specifically stated in the body of the inspection report.
Condition Report
93-137
Plant Electrical Equipment May Be Used in
Applications Beyond Fault Current Ratings
March 30, 1993
97-0249 (Quality
Condition Report
(QCR))
Process Improvements SPEED NP 9.3.3
October 30, 1997
98-1004
SI Accumulator Level Decrease
March 11, 1998
99-2346
Seismic Qualification of Service Water
Pump Column Bolting Questioned
October 6, 1999
00-0094
Plant Electrical Equipment May Be Placed
Into Alignments Beyond Equipment Fault
Current Ratings
January 7, 2000
00-0128
P-32F-M Thermocouple Installation Not
Properly Documented
January 11, 2000
00-0213
Low Forebay Level, Lowest -9.6', Trip
January 20, 2000
00-0494
CR History of CIM Concerns
February 10, 2000
00-0514
QA Classification of Packing Kit for 850
Hydraulic Cylinder Questioned
February 9, 2000
00-0834
Corrosion Inhibitor Used in G-01 Without
the Required Evaluation
March 9, 2000
00-2077
Procurement Evaluation Deficiencies
June 16, 2000
00-2312
Commercial Grade Dedication Program
August 1, 2000
00-2335
Abnormal Sound From P-32A Service
Water Pump
August 3, 2000
00-2423
Dedication Criteria Changed During Receipt
Inspection
August 10, 2000
00-2426
Lack of As Found Data During Receipt
Inspection
August 10, 2000
11
00-2427
Documenting Discrepancies During Receipt
Inspection
August 10, 2000
00-2428
Technical Evaluations Dont Address
Equipment Qualification
August 10, 2000
00-2792
Less Than Adequate Wire Storage, QA
Versus Non-QA
September 20, 2000
00-2812
Alert and Notification System (ANS) Siren
Failure Response Weak
September 22, 2000
00-2933
Form for QA Conditional Release Form
Doesnt Match Procedure
September 29, 2000
00-2948
Crib Freeze Event CAs Concerns
October 2, 2002
00-3079
Condenser Steam Dump Malfunction
October 13, 2000
00-3299
Damaged Breaker Auxiliary Switches
October 23, 2000
00-4014
Leak On Unit 2 Conoseals
December 30, 2000
00-4150
Electrical Perturbation On Unit 2 Generator
December 17, 2000
01-0001
Unexpected Alarm During Service Water
Pump Start
January 1, 2001
01-0003
TS-33 Problems Due To Failing Pressure
Indicator
January 2, 2001
01-0022
Less Than Adequate Work Plan To Thaw
Frozen Pipe
December 29, 2000
01-0030
Service Water Pump Expansion Joints
January 3, 2001
01-0039
Service Water Pump Expansion Joints
January 3, 2001
01-0048
P-32C Work Packages Not Ready
January 5, 2001
01-0102
Less Than Adequate Evaluation of Part 21
NUTRK Item - AGASTAT
January 10, 2001
01-0109
Rope And Wood On Service Water Piping
January 12, 2001
01-0111
Untimely CR Initiation by OA Personnel
January 11, 2001
01-0112
Replacement Service Water Pump Motors
January 12, 2001
01-0122
Apparent Cause Evaluation Action Not
Created
January 12, 2001
01-0148
Wrong Thermocouple Extension Cable
Installed
January 16, 2001
12
01-0203
4 KV System Grounds
January 19, 2001
01-0216
New Thermocouple Found Faulty
January 19, 2001
01-0220
Incomplete IWP
January 21, 2001
01-0241
CRs Not Written as Result of
Self-Assessment
January 23, 2001
01-0259
West Service Water Supply Isolation Valve
Installation
January 24, 2001
01-0289
Service Water Safety Monitor Assumptions
January 27, 2001
01-0301
CR Trend Review Problems
January 29, 2001
01-0307
Service Water Pressure Indicator
January 30, 2001
01-0310
SW-2930A Valve Body Pitted
January 30, 2001
01-0318
No VT-2 Qualified Individual On Shift When
Required
January 30, 2001
01-0319
Less Than Adequate Work Plan SFP HX
[Spent Fuel Pool Heat Exchanger] Inlet
Valve
January 30, 2001
01-0323
Temp Change To AOP 9A Concern
January 30, 2001
01-0330
Declining Vendor Performance - IPSCO
February 1, 2001
01-0335
Increased Magnitude Of Change In SW
[Service Water] Pump Vibration Readings
February 1, 2001
01-0338
CAP Procedure Violations
February 1, 2001
01-0341
SW Line Stop Less Than Affective
February 1, 2001
01-0344
Service Water Expansion Joint - Spare
Parts Wrong Size
February 2, 2001
01-0365
Valve Accessibility Questioned
February 3, 2001
01-0368
Unit 2 Rise in Power - Dilution for Unit 1
February 2, 2001
01-0369
Energy Had Been Verified Released For
Tag Series O SW SW-2927A OP REV 2-1
By The Work Group, But No One From The
Work Group Signed On
February 2, 2001
01-0377
CR Routing and Closing
February 6, 2001
01-0380
Line Stop Machines Installation Delays
February 5, 2001
13
01-0387
SW-2974B Work Schedule Of 2/5/01 Parts
Issue
February 5, 2001
01-0395
Untimely Corrective Action
February 6, 2001
01-0403
Inadequate Safety Screening
February 8, 2001
01-0407
Line Stop Seal Failure
February 7, 2001
01-0418
Procedure Sign Off Sequence Not Used
February 8, 2001
01-0421
Service Water Piping Degradation
February 8, 2001
01-0423
4160 VAC Breaker Damage
February 8, 2001
01-0425
Package Release Without Tag Series
Accepted
February 8, 2001
01-0429
Classification of CR 01-0368
February 9, 2001
01-0438
Ineffective Followup on RCE 00-007 Actions
January 10, 2001
01-0444
Service Water System Piping Contaminated
February 9, 2001
01-0448
Containment Fan Cooler SW Flow Out Of
Spec
February 13, 2001
01-0449
NUTRK Not User-Friendly
February 13, 2001
01-0452
Micrologger Routes Erased
February 12, 2001
01-0454
U2 'A' Safety Injection SI Accumulator Level
February 12, 2001
01-0457
Service Water Gauge Out Of Tolerance
February 12, 2001
01-0471
Accumulator Level Indicator Failing
February 14, 2001
01-0481
Storage Of Spare SW Pump Motors
February 14, 2001
01-0529
Corrective Action Not Incorporated
February 20, 2001
01-0552
New Piping Insulation Damaged
February 22, 2001
01-0572
SI Accumulator Level Spikes
February 22, 2001
01-0587
Documentation Of Service Water System
Test
February 26, 2001
01-0596
Welder Bypassed Hold Point
February 26, 2001
01-0605
QCR Closed Prior to Actions Being
Completed
February 26, 2001
01-0612
Less Than Adequate Indication On 'F'
Service Water Pump Ammeter
February 27, 2001
14
01-0618
Corrective Action Program CAP Self-
Assessment Issues
February 28, 2001
01-0634
RCE 00-067 Corrective Actions
July 1, 2001
01-0635
Priorities Not Assigned in NUTRK
March 1, 2001
01-0638
SW Mod Work Caused Vacuum Loss
March 1, 2001
01-0639
SW Mod Work Caused Air In-leakage
March 1, 2001
01-0651
Less Than Adequate Closure of Condition
Reports
March 5, 2001
01-0662
Overdue Corrective Action
March 5, 2001
01-0693
CIM Not Updated To Reflect New Type
After Coolers
March 7, 2001
01-0697
Condition Report Actions Not Adequately
Dispositioned - CR 98-1161
March 6, 2001
01-0705
Exact Time 'C' CCW [Component Cooling
Water] Returned To Service Unknown
March 9, 2001
01-0706
New SW Valves Not Shown On Any
Controlling Diagrams
March 9, 2001
01-0731
Inappropriate Closure of Action
March 12, 2001
01-0733
OA Witness Of Shipment
March 10, 2001
01-0734
Service Water Motor Shipped
Inappropriately
March 9, 2001
01-0738
Abnormal Noise From P-32A
March 11, 2001
01-0761
CFC [Containment Fan Cooler] Flow
Outside Of Band
March 13, 2001
01-0768
NUTRK Anonymous Notification
March 12, 2001
01-0782
SW Pump Motor Replacement Problems
Initiated 3/14/01
01-0794
Service Water Motor SPEED Insufficient
March 13, 2001
01-0817
SI Accumulator Fill Concerns
March 15, 2001
01-0818
Incomplete Weld Exam On Containment
Fan Cooler
March 15, 2001
01-0821
P32C-M Locked Rotor Test Results
March 15, 2001
01-0852
Drawings Reflect Wrong Valve Positions
March 16, 2001
01-0870
Weld Data Sheets Not Complete
March 21, 2001
15
01-0903
Procedure Misaligned Valves
March 22, 2001
01-0911
Additional Information Provided By
Engineering - Operability Of P-32C Drawn
Into Question
March 20, 2001
01-0919
Wrong Component Danger Tagged
March 22, 2001
01-0952
Incorrect Valve Labels
March 26, 2001
01-0958
Potential Valve Failure - Valve Stem
Separation
March 26, 2001
01-0983
Containment Fan Cooling Flexible Piping
Concern
March 28, 2001
01-1001
Less Than Adequate Formal Documentation
and Tracking of Effectiveness Review
Actions
March 30, 2001
01-1027
Overdue Condition Reports
April 3, 2001
01-1032
RWST Level Transmitter Found Out of
Calibration
April 2, 2001
01-1046
Evaluation Actions Not Documented in
NUTRK
April 4, 2001
01-1047
NRC/PI&R Inspection Concern of CR Cross
Referencing
April 3, 2001
01-1048
NRC/PI&R Inspection Concerns Less Than
Adequate SRO Screenings
April 3, 2001
01-1059
Found Local Control Switch
For 1A52-84, 1A06 Feed to 1X14
Transformer, In The Pullout Position. Per
PC 43 Part 2
April 3, 2001
01-1073
Lost/Misplaced Condition Report
April 4, 2001
01-1105
MOV Failed to Shut Remotely
April 5, 2001
01-1131
Condition Report Closure Inappropriate
April 6, 2001
01-1137
Breaker Charging Spring Failed To
Discharge
April 7, 2001
01-1146
Hoses Not Used For Draining Systems
April 9, 2001
01-1150
Breaker Inseat Not Updated In Champs
April 9, 2001
01-1178
Heat Exchangers Opened Prior To
Scheduled
April 17, 2001
16
01-1210
Service Water Valve Has Significant Leak
April 11, 2001
01-1244
U2 Service Water Leak On A Containment
Fan Cooler
April 11, 2001
01-1270
High Heat Exchanger Flow Rate
April 13, 2001
01-1279
Less Than Adequate Specified
Post-Maintenance Testing
April 14, 2001
01-1297
Coordination Of Work Activities
MR 98-024*J
April 14, 2001
01-1319
Containment Fan Cooler Outlet Throttle
Valve Potential Part 21
April 17, 2001
01-1334
SW-2880 Signature Indicates Valve Stem
Bent
April 18, 2001
01-1339
Closed Work Order - ASME Discrepancies
April 18, 2001
01-1363
Valves Pre-fabricated Backwards
April 19, 2001
01-1394
Pressure Test Data
April 21, 2001
01-1402
ANII Hold Points Bypassed
April 20, 2001
01-1453
No Oil in 1P-15A Sightglass
April 24, 2001
01-1470
Operations Adverse Trend
April 24, 2001
01-1471
Potentially Decreased Performance
April 24, 2001
01-1482
Bus And Breaker Short Circuit Rating
Discrepancies
April 25, 2001
01-1492
LTA communication on RP Close Out of a
CR
April 26, 2001
01-1551
Lack of Timely CR Initiation
April 30, 2001
01-1556
Condition Report Priority LTA
May 1, 2001
01-1568
Questioning Proper Installation Of CFC Ball
Valves
May 1, 2001
01-1577
Work Order LCO Tracking
May 1, 2001
01-1599
Trend Report Finding
May 4, 2001
01-1600
Potential Adverse Trend in NDE
[Non-Destructive Evaluation]
May 4, 2001
01-1601
Adverse Trend in Warehouse Fire
Protection
May 4, 2001
17
01-1602
Error Mode Classifications
May 4, 2001
01-1615
Service Water Flow Instrument Misaligned
May 2, 2001
01-1631
Effectiveness Review of RCE
May 4, 2001
01-1650
Ops Increase Error Rate - Skill Based
Errors
May 5, 2001
01-1677
Coating On Containment Fan Coolers
Questioned
May 7, 2001
01-1678
Support In Containment Has Unqualified
Coating
May 1, 2001
01-1688
TS-76 Concerns
May 9, 2001
01-1698
Overdue Corrective Actions
May 9, 2001
01-1718
Valve Repair Work Inadequacies
May 10, 2001
01-1723
Work Order Documentation Inadequate
May 10, 2001
01-1834
Maintenance Corrective Action Item Due
Date Extensions Not Documented
May 21, 2001
01-1851
Missing RRM Documentation For
Completed Work
May 23, 2001
01-1856
G01 HX Corrosion
May 23, 2001
01-1902
Corrective Actions For CR 00-1812 Do Not
Address Concern
May 24, 2001
01-1962
Condition Report (CR) Without Priorities
June 4, 2001
01-1963
Piping Class Incorrectly Shown On P&ID
June 5, 2001
01-1966
QA/SR RWST Level Transmitter Out of
Calibration
June 4, 2001
01-1994
OD Part II for CR 01-1559 Not Completed in
30 Days as Required
June 6, 2001
01-2035
Lesson Plan Not Revised Per Condition
Report
June 12, 2001
01-2160
Corrective Action Program Weakness
June 26, 2001
01-2085
Safety Injection Pump Motor Bearing Had
No Oil Visible in Fill Connection
June 17, 2001
01-2104
Insufficient Copper Tubing In Reserve For
Work Order
June 18, 2001
18
01-2142
U1 Safety Injection Accumulator Level Out
of Calibration
June 24, 2001
01-2166
Service Water Isolation Valve Leaks
Through
June 27, 2001
01-2168
Service Water Zurn Strainer Inoperable
June 26, 2001
01-2170
Potential Conflict With Service Water LCOs
June 26, 2001
01-2178
Large Fish Kill Results In Unit 2 Trip
June 28, 2001
01-2181
Emergent Temp Change To AOP
June 27, 2001
01-2191
Two Tag Series In Effect For Same Job
June 27, 2001
01-2237
CR 00-3888 Corrective Action Not
Completed
July 2, 2001
01-2243
Revision of Operability Determination
Contains Deficiencies
July 3, 2001
01-2264
Corrective Actions Without Assigned
Priorities
July 3, 2001
01-2267
Scheduled Conflict Would Have Caused
LCO Entry
July 5, 2001
01-2283
Corrective Action Items Overdue
July 9, 2001
01-2337
Rework Of Circ Water Seal Supply Strainer
July 13, 2001
01-2384
Less Than Adequate Closeout of Condition
Report Dealing With Alarm Response Book
Adequacy
July 19, 2001
01-2386
Unknown White Residue On Refueling
Water Storage Tank
July 19, 2001
01-2406
Blockage Of Emergency Diesel Generator
Cooler Tubes
July 23, 2001
01-2426
Hole In U1 [Unit 1] Refueling Water Storage
Tank
July 25, 2001
01-2487
Priorities Not Assigned As Required to
Condition Reports
August 3, 2001
01-2526
Ineffective Corrective Action - Failure To
Test Redundant Emergency Diesel
Generator
August 8, 2001
01-2598
AM 3-4 Obsolete Revision of 10 CFR 50.65
August 16, 2001
19
01-2705
Nuclear Safety Analysis NSA Adverse CR
Trend
August 29, 2001
01-2707
Condition Report Closed With Uncompleted
Corrective Actions
August 29, 2001
01-2721
Condition Reports Did Not Determine if
Functional Failures Were Maintenance
Preventable
August 29, 2001
01-2771
NUTRK Items Without Priority Assigned
September 7, 2001
01-2781
Damaged Auxiliary Switch On 4 KV Breaker
A52-DHVR-1200-31
September 8, 2001
01-2799
Errors In Drawing For G-02 Metering, DCNs
Not Done
September 9, 2001
01-2810
Potential Adverse Trend in Q List Program
September 11, 2001
01-2918
Evaluation Due Dates
September 24, 2001
01-2927
Schedule Plant to Revise Refueling
Procedures to Include Improved Technical
Specifications (ITS)
September 25, 2001
01-2929
Condition Report Closed Without
Consideration of Apparent Cause
Evaluation Recommendations
September 28, 2001
01-2969
Potential Current Transformer Issue In
1A52-59 Cubicle
September 26, 2001
01-2994
Less Than Adequate Support For MCE
Testing Of Unit 2 SI Pump Motor
October 2, 2001
01-3039
Operability Determinations Not Reviewed
For ITS Implications
October 5, 2001
01-3058
Condition Reports With No Assigned Priority
October 9, 2001
01-3107
Less Than Adequate Apparent Cause
Evaluation and Follow-up Actions
October 10, 2001
01-3148
Diesel Testing Not Identified In
Schedule/Test Plan
October 16, 2001
01-3166
Inadequate Closure of Condition Report CR
01-1329 - FPEE On Modified Fire Damper
October 16, 2001
01-3174
Grounding Card Latch Mechanism Difficult
To Verify Engaged
January 18, 2001
01-3199
SRO Screening Issues With CR 01-3139
October 19, 2001
20
01-3258
Safety-Related Bus Voltages High - 7 day
LCO Entered
November 21, 2001
01-3284
Condition Reports Threshold for EP Issues
October 26, 2001
01-3357
NUTRK Actions Not Prioritized
November 5, 2001
01-3414
7% Condition Report Items Overdue
November 9, 2001
01-3492
Problems With CR 00-1039 Resolution
November 15, 2001
01-3545
Procedures Indicate LCO Is Required May
Be Incorrect
November 26, 2001
01-3606
CR Verification Not Completed in Timely
Manner
November 30, 2001
01-3626
Less Than Adequate Documentation To
Support Operability Determination
December 3, 2001
01-3678
Condition Reports Priority -100
December 7, 2001
Operability Determination (OD)
OD for CR 93-0137
Plant Electrical Equipment May Be Used in
Applications Beyond Fault Current Ratings
Revision 8
August 6, 2001
OD for CR 00-3299
Chipped Auxiliary Switch On Breaker
A52-DHVR-1200-15
October, 2000
OD for CR 99-2346
SW Pump Discharge Column Connections
March 6, 2001
OD for CR 01-1105
MOV Failed to Shut Remotely
April 6, 2001
Drawing Number
PB 31 E APS 240 052
09
Schematic Diagram
4160V SWGR Bus 1-A06 (2-A06)
Feeder Breaker 1A52-84 (2A52-89 to STA
Service XFMR IX-14 (2X-14)
Revision D
PB 02 E SIS 000 002
06
Elementary Wiring Diagram
4160V SWGR.2A05 Cubicle-74 Safety
Injection Pump 2P-015A
PBNP Unit 2
Revision D
PB 01 E APS 256 004
01
Elementary Wiring Diagram
4160 Switchgear Cubicle-58 Station Service
Transformer Breaker 1A-52-58
PBNP Unit 1
Revision E
21
PB 01 E APW 240
034 03
Connection Diagram
4160V Switchgear 1A05-Cubicle 58
Station Service Transformer 1X-13
Revision E
PB 01 E APS 03015
07
Elementary Wiring Diagram
4160 SWGR 1A05-Cubicle 57
Bus Tie Breaker 1A52-57
Revision E
PB 01 E APS 031 001
11
Elementary Wiring Diagram
4160 Switchgear Cubicle 60
Emergency Generator Breaker 1A52-60
PBNP Unit 1
Revision E
PB 01 E APS 031 002
05
Elementary Wiring Diagram
Alternative Power to 1A-05 from G02 EDG
Breaker 1A52-66
PBNP Unit 1
Revision E
PB 01 E RPS 141
078 18
Schematic Diagram
SI Logic Engineered Safety Features
(ESF) Systems Train A
Reactor Safeguards Systems
PBNP Unit 1
Revision E
SK-M-21-2
Refueling Water Storage Tank - 1-T13,
2-T13
Revision 0
PB 01 MSIG 246 001
05
1-T13 RWST Assembly And Details
Revision E
Action Request (AR)
AR ACE000251
Tag Series Changes And Loss Of
Awareness Of Clearance Status
October 22, 2001
AR ACE000260
G-04 Low Oil Level
October 30, 2001
AR ACE000294
Resistance Readings May Be Affected By
Nomex Wear
November 14, 2001
AR ACE000299
IP-29 Turbine-Driven Auxiliary Feedwater
Pump Spurious Overspeed Trips
November 20, 2001
AR ACE000321
Wrong Oil Used In Auxiliary Feedwater
Turbine Bearings
December 11, 2001
AR ACE000325
Unanticipated Outward Rod Motion
December 13, 2001
AR ACE000327
Component Cooling Water Pump Oil
Sample Results
December 17, 2001
22
AR ACE000496
Plant Electrical Equipment May Be Used in
Applications Beyond Fault Ratings
April 1, 1993
AR ACE000497
4160V and 480V System Operating
Voltages Are Significantly Higher Than the
Nominal System Voltages
December 3, 1997
AR ACE000498
Operating the 480V System at Voltage
Magnitudes Higher Than 500V Causes
Equipment to be Derated From Ratings at
480V to Ratings at 600V for Fault Current
December 3, 1997
AR ACE000499
System Model Should be Revised With
Plant Operations to Determine More
Realistic Equipment Alignments
December 3, 1997
AR ACE000500
Additional Scenarios Should be Analyzed
and Existing Scenarios Should be Revised
to More Accurately Reflect How PBNP is
Operated
December 3, 1997
AR ACE000526
Missed Surveillance For PAM Core Exit
T/Cs
December 14, 2001
AR CA001184
Extent of Condition Review of Other
SPEEDs
March 15, 2001
AR CA001193
Reinforce Managements Expectations That
Requirements of Administrative Procedures
Are to be Complied With
July 3, 2001
AR CA001461
Bus And Breaker Short Circuit Rating
Discrepancies
April 30, 2001
AR CA001634
Dilution of Accountability for Programs for
Vendor Technical Information Program and
Component Instruction Manual
June 5, 2001
AR CA003148
Revise NP 9.3.3
November 25, 1997
AR CA003235
Review the Calculations for Each Breaker or
Other Piece of Switchgear That is
Calculated to be Overloaded
March 16, 1994
AR CA003236
Write and Submit an LER for Condition of
Plant Electrical Equipment May Be Used in
Applications Beyond Fault Ratings
July 10, 1997
23
AR CA003237
Complete a Revision to the Operability
Determination to Address: Equipment
Removed From the List, Equipment Which
May Experience Fault Currents of Higher
Magnitude, and Equipment Added to the
List Attached to the New Fault Duty
Calculation
December 3, 1997
AR CA003238
The SSC in the Operability Determination
for This CR [93-137] Have Been Determined
to be Operable, But Degraded
March 26, 1998
AR CA003239
Document That the Operability
Determination to Supported Bolted Shorts
as Described in CR 93-137 Reflects Most
Recent Review
September 11, 2000
AR CA003240
Finalize and Issue the New Preliminary
Short Circuit Calculations Based on
Procedure Changes to be Completed Per
CR 00-0094
September 11, 2000
AR CA003242
Request a Schedule and Justification be
Provided for Which One of the Four Options
That Are Being Considered as Possible
Solutions to the Bolted Fault Issue
August 14, 2001
AR CA003518
NRC 50.59 Inspection Requested A
Procedural Tie Be Created In IT-21 And
IT-22, Back To TRM Section 3.5.1
January 16, 2002
AR CA002130
Potential Adverse Trend in Q List Program
September 13, 2001
AR CAP000126
Short Circuit Fault Current Calculations
January 7, 2000
AR CAP000726
Corrective Actions For CR 00-1812 Do Not
Address Concern
May 24, 2001
AR CAP001532
Plant Electrical Equipment May Be Used in
Applications Beyond Fault Rating
March 30, 1993
AR CAP001877
FSAR Discrepancy On Definition Of Reg
Guide Category 2
January 16, 2002
AR CAP001886
Incomplete 50.59 Screening Answer For
Changes To Relief Valve CC-736A/B
January 16, 2002
AR CAP001897
Letdown Isolation Valve Appendix R
Operation During Degraded Voltage
Conditions
January 17, 2002
AR CAP001900
Incomplete Corrective Actions Regarding
Classification Of RC-427
January 17, 2002
24
AR CAP001901
FSAR Chapter 9 Changes For CFC Service
Water Pressure Not Also Made In Chapter 6
January 17, 2002
AR CAP001910
Safety Evaluation 2000-0014 Incomplete
January 17, 2002
AR CAP001915
Questioning Corrective Action For
CR 00-2859 On Screening Procedure Temp
Change
January 18, 2002
AR CAP001916
Incorrect Answer To Tech Spec Change
Question In 50.59 Evaluation
January 18, 2002
AR CAP001957
Individual Requested To Do Work Not
Qualified Or Trained To Do
January 24, 2002
AR CAP001962
WO For SR Equipment Bypassed QC
Review
January 24, 2002
AR CAP001965
SW Pumps Discharge Expansion Joints
Have Surface Cracks
January 25, 2002
AR CAP001966
Outdated Procedures For New PPCS, With
No New Procedures In Place
January 25, 2002
AR CAP001970
Poor Loading Of E-12 (SO4B2) Work Week
January 25, 2002
AR CAP001979
Minor Deficiencies In The Corrective Action
Program
January 25, 2002
AR CAP001984
Negative Trend Of Security Self Reporting
Issues In Corrective Action System
January 25, 2002
AR CAP001985
NRC Commitment To Inspection Unit 2
Internals Lift Rig Not Met
January 25, 2002
AR CAP001992
NUTRK Database Is Inaccurate
And Cluttered With Outdated Action
Requests
January 28, 2002
AR CAP001996
Lack Of Documentation Of Adverse Issues
January 28, 2002
AR CAP002031
NP5.3.1 Does Not Allow Closure Of ARs To
Other Formal Tracking Mechanisms
January 30, 2002
AR CAP002038
Questionable Acceptable Voltage Ranges
For Instrument Buses
January 31, 2002
AR CAP002039
Vibration Indications On G-01
January 31, 2002
AR CAP002065
CAP Closed Without All Corrective Actions
Completed
February 4, 2002
AR CAP002083
P-032D Service Water Pump Vibration And
Shaft Wear Resolution
February 5, 2002
25
AR CAP002264
Untimely Implementation of
Recommendations From IN 88-023-05
February 21, 2002
Lists
List of Apparent Cause Evaluations - 2001
2001
List of Completed Root Cause Evaluations -
2001
2001
List of Temporary Modifications - 2001
January 3, 2002
Root Cause Evaluations (RCEs)98-190
Inappropriate Design Pressure For The AFW
[Auxiliary Feedwater] Discharge Valve
Modification
Revision 1
98-214
Disabled Service Water Pump Auto Start
Feature On EDG [Emergency Diesel
Generator] Breaker Closure Results in
Missed LCO
November 30, 2001
00-104
Common Cause Assessment for Procedure
Quality Issues
March 2, 2001
01-013
Speed For P-32C Service Water Pump
Motor
01-013
Replacement Service Water Pump Motor
Does Not Meet Design Requirements
June 8, 2001
01-033
Maintenance Rule Component Common
Cause
May 8, 2001
01-046
Unit 1 Loss Of Inverter
July 18, 2001
01-047
Unit 1 Main Feed Pump Inboard Bearing
Failure
July 19, 2001
01-0151
G04 Generator Failure Equipment Rood
Cause
August 5, 2001
01-052
Failure To Perform TS Required EDG
Testing
August 9, 2001
01-055
Reactor Coolant Pump Seal Malfunction
Caused Unit Shutdown
September 6, 2001
26
Nuclear Plant Memorandum (NPM)
2002-0006
Minutes From The December 19, 2001
CARB Meeting
January 4, 2002
2002-0052
Third Quarter 2001 Corrective Action
Program Trends
January 28, 2002
2002-0056
CARB Agenda For The February 5, 2002
Meeting
February 1, 2002
Work Orders
9924742
Temporary Relocate 1LT-972/1LI-921 to
Allow for Installation of Welds and
Anchorage on RWST, Then Return to
Original Locations
April 14, 2001
9937026
Transmitter Enclosure is Damaged,
Condition Report Submitted
April 2, 2001
9945054
IT-013 Repair Weld
July 24, 2001
9945202
IT-13 Clean Residue/Insp 2 Day Later
July 19, 2001
Plant Modifications
MR-99-040
Unit 1 RWST Seismic Upgrade
July 12, 2000
Engineering Work Request (EWR)02-019
Protective Enclosure for Sightglass/Oiler
Assemblies
January 25, 2002
Nuclear Power Business Unit Procedures (NPs)
5.3.1
Action Request Process
Revision 19
5.3.7
Revision 8
5.4.1
Open Item Tracking System (NUTRK)
Revision 11
9.3.3
Spare Parts Equivalency Evaluation [SPEED]
Revisions 2 and 3
9.8.1
Specification Preparation, review, and
Approval Process
Revision 0
27
9.8.2
Technical Review and Approval of
Requisitions
Revisions 0 and 1
9.8.4
Safety Classification of Sub-Components
and Materials
Revision 0
9.8.5
Dedication of Commercial Grade Items
Revisions 0 and 1
9.8.6
Conditional Release of QA-related Items and
Services
Revision 0
9.8.9
Product Technical Information
Revision 0
9.9.2
Quality Receipt
Revision 0
9.9.3
Spare Parts Equivalency Evaluation [SPEED]
Revisions 2 and 3
9.10.1
Warehouse Material Issue
Revision 0
10.2.4
Work Order Processing
Revision 7
Other Procedures and Documents
AM (Administrative
Manual) 3-4
Implementation of the Maintenance Rule at
PBNP
Revision 4
A-P-01-17
Improved Technical Specifications Audit
October 5, 2001
A-P-01-018
Maintenance Rule Audit
August 28, 2001
FP-NO-SQ-01
Performance of Supplier Audits/Surveys
Revision 1
FP-SC-GEN-01
Procurement - General
Revision 1
FP-SC-RSI-01
Receiving
Revision 0
FP-SC-RSI-02
Quality Receipt
Revision 0
FP-SC-RSI-03
Procurement Deficiency Reports
Revision 0
Licensee Event
Report 97-032
Inadequately Rated Electrical Buses Could
Disable Switchgear and Cause Secondary
Fires That Prevent Safe Shutdown Per
Appendix R
July 30, 1997
OEG (OE Group
Guide) 001
Root Cause Evaluation
Revision 6
OEG 003
Corrective Action Program Guidance
Revision 2
PBF (Point Beach
Form)-0026q
Procedure Preparer/Technical Reviewer
Checklist
Revision 4
PBF-0026r
Procedure Validation
Revision 1
28
PBF-1531
Conditional Release Request
Revision 2
PBF-1583
Design Verification Notice
Revision 1
PBF-1586b
CI Manual Distribution
S-A-CA-01-01
Assessment of Point Beach Corrective
Action Program
February 2001
Spare Parts
Equivalency
Evaluation Document
2002-006
Replace Obsolete Westinghouse Motor With
Equivalent Marathon Electric Motor
February 8, 2002
Nuclear Oversight Quarterly Reports
1st, 2nd, and 3rd
Quarters, 2001
Corrective Action Program Performance
Indicators
October, November,
December 2001;
January 2002
Bolted Fault Meeting Minutes
January 21, 2002
Project Work Plan: Bolted AC Fault Issue
Revision 3
August 28, 2000
AC Bolted Fault Project History and Timeline
2001
Electrical Fault Overduty Resolution Plan
Updates
May and November
2001; February
2002
SI Pump Gas Binding Event Operating
Experience Review
February 23, 2002
Corrective Action Trend Reports
1st, 2nd, and 3rd
Quarters, 2001
Corrective Action Review Board Member
Attendance Records
Chemistry Logs
Unit 1 RWST Chemical Analyses
February 5, 2002
NUTRK Operating
Experience Review
NRC Information Notice 88-023, Potential
for Gas Binding of High Pressure Safety
Injection Pumps During a Loss-of-Coolant
Accident, Original Notice and 5
Supplements
May 12, 1988
January 5, 1989
January 30, 1990
December 10, 1990
December 18, 1992
September 1, 1999
NUTRK Operating
Experience Review
NRC Information Notice 97-040, Potential
Nitrogen Accumulation Resulting From
Backleakage From Safety Injection Tanks
June 26, 1997
29
NUTRK Operating
Experience Review
SOER 97-01, Potential Loss of High
Pressure Injection and Charging Capability
From Gas Intrusion
December 6, 1997
NUTRK Operating
Experience Review
SEN 179, Long-Standing Design
Weaknesses and Ineffective Corrective
Actions Cause Gas Binding Failures of High
Head Safety Injection Pumps
January 29, 1998
NUTRK Operating
Experience Review
OE 8830, Potential Nitrogen Voiding and
Water Hammer in the Low Pressure Safety
Injection System
March 26, 1998
NUTRK Operating
Experience Review
OE 9876, 4B HHSI Pump Gas Binding
May 4, 1999
Plant Internal Letter
NEPB-88-252
NRC Information Notice No. 88-23: Potential
For Gas Binding of High-Pressure Safety
Injection Pumps During A Loss-of-Coolant
Accident
June 7, 1988
Plant Internal Letter
NEM-89-143
NRC Information Notice No. 88-23,
Supplement 1: Potential For Gas Binding of
High-Pressure Safety Injection Pumps
During Loss-of-Coolant Accident
March 6, 1989
Plant Internal Letter
NEM-90-368
NRC Information Notice No. 88-23
Supplement 2: Potential For Gas Binding of
High-Pressure Safety Injection Pumps
During A Loss-of-Coolant Accident
April 23, 1990
Plant Internal Letter
NPM 91-0400
NRC Information Notice No. 88-23,
Supplement 3: Potential For Gas Binding of
High-Pressure Injection Pumps During A
Loss-of-Coolant Accident
June 18, 1991
Plant Internal Letter
NPM 93-0092
NRC Information Notice No. 88-23,
Supplement 4: Potential For Gas Binding of
High-Pressure Safety Injection Pumps
During A Design Basis Accident
February 5, 1993
30
DOCUMENTS REQUESTED FROM THE LICENSEE PRIOR TO ONSITE INSPECTION
Two copies of administrative procedures related to:
corrective action program
work orders
root cause analysis
procedure change, use, and adherence
One copy of audits and self-assessments conducted since January 1, 2001, in the following
areas:
corrective action process
maintenance/work control
operations
engineering
One copy of minutes for onsite and offsite committee meetings, including the Corrective Actions
Review Board, conducted since January 1, 2001
Two copies of a listing of:
root cause evaluations completed since January 1, 2001
CRs generated since January 1, 2001, related to corrective actions
work orders and CRs generated since January 1, 2001, related to the service
water, safety injection, and the 4160-volt systems