ML020850432

IR 05000266/2002-003; 05000301/2002-003, on 1/22-2/25/2002. Nuclear Management Company, LLC, Point Beach Nuclear Plant, Baseline Inspection of the Identification and Resolution of Problems. No Violations Noted

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

License Nos. DPR-24; DPR-27

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

DFT

BAW

RidsNrrDipmIipb

GEG

HBC

PGK1

C. Ariano (hard copy)

DRPIII

DRSIII

PLB1

JRK1

U.S. NUCLEAR REGULATORY COMMISSION

REGION III

Docket Nos:

50-266; 50-301

License Nos:

DPR-24; DPR-27

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

URI

2P-15B Safety Injection Pump Failure During Monthly

Preventative Maintenance Lubrication Activity

Closed

None

Discussed

None

9

LIST OF ACRONYMS USED

ACE

Apparent Cause Evaluation

AR

Action Request

ASME

American Society of Mechanical Engineers

CA

Corrective Action

CAP

Corrective Action Program

CARB

Corrective Action Review Board

CR

Condition Report

DC

Direct Current

EDG

Emergency Diesel Generator

EOP

Emergency Operating Procedure

EWR

Engineering Work Request

FSAR

Final Safety Analysis Report

INPO

Institute of Nuclear Power Operations

KPB

Kewaunee-Point Beach

KV

Kilovolt

LCO

Limiting Condition for Operation

LER

Licensee Event Report

LTA

Less Than Adequate

MOV

Motor-Operated Valve

NCV

Non-Cited Violation

NMC

Nuclear Management Company, LLC

NP

Nuclear Power Business Unit Procedure

OA

Organizational Assessment

OE

Operating Experience

OI

Operating Instruction

OOS

Out-Of-Service

PBNP

Point Beach Nuclear Plant

PMT

Post-Maintenance Testing

psi

Pounds Per Square Inch

QA

Quality Assurance

QCR

Quality Condition Report

RCE

Root Cause Evaluation

RCP

Reactor Coolant Pump

SDP

Significance Determination Process

SRO

Senior Reactor Operator

SW

Service Water

TS

Technical Specification

V

Volt

WO

Work Order 10

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

Operability Determinations

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

operability determinations

temporary modifications

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

temporary modifications

operability determinations