ML020380210
| ML020380210 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/06/2002 |
| From: | Gardner R NRC/RGN-III/DRS/EEB |
| To: | Reddemann M Nuclear Management Co |
| References | |
| IR-02-002 | |
| Download: ML020380210 (20) | |
See also: IR 05000301/2002002
Text
February 6, 2002
Mr. M. Reddemann
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 50-266/02-002(DRS); 50-301/02-002(DRS)
Dear Mr. Reddemann:
On January 18, 2002, the NRC completed an inspection at your Point Beach Nuclear Plant.
The enclosed report documents the inspection findings which were discussed on January 18,
2002, with Mr. Taylor and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and
compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed
personnel. Specifically, this inspection focused on the baseline annual inspection for
evaluations of changes, tests, or experiments (10 CFR 50.59) and the baseline biennial
inspection for permanent plant modifications.
No findings of significance were identified.
In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter
and its enclosure will be available electronically for public inspection in the NRC Public
Document Room or from the Publicly Available Records (PARS) component of NRC's
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/
Ronald N. Gardner, Chief
Electrical Engineering Branch
Division of Reactor Safety
Docket Nos. 50-266; 50-301
Enclosure: Inspection Report 50-266/02-002(DRS); 50-301/02-002(DRS)
See Attached Distribution
M. Reddemann -2-
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
Mr. M. Reddemann
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 50-266/02-002(DRS); 50-301/02-002(DRS)
Dear Mr. Reddemann:
On January 18, 2002, the NRC completed an inspection at your Point Beach Nuclear Plant.
The enclosed report documents the inspection findings which were discussed on January 18,
2002, with Mr. Taylor and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and
compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed
personnel. Specifically, this inspection focused on the baseline annual inspection for
evaluations of changes, tests, or experiments (10 CFR 50.59) and the baseline biennial
inspection for permanent plant modifications.
No findings of significance were identified.
In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter
and its enclosure will be available electronically for public inspection in the NRC Public
Document Room or from the Publicly Available Records (PARS) component of NRC's
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/
Ronald N. Gardner, Chief
Electrical Engineering Branch
Division of Reactor Safety
Docket Nos. 50-266; 50-301
Enclosure: Inspection Report 50-266/02-002(DRS); 50-301/02-002(DRS)
See Attached Distribution
DOCUMENT NAME: C:\MYFILES\Copies\Point Beach Drs.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 E RIII RIII
NAME GHausman:jb RLanksbury RGardner
DATE 02/05/02 02/06/02 02/06/02
OFFICIAL RECORD COPY
M. Reddemann -2-
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
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
Report No: 50-266/02-002(DRS); 50-301/02-002(DRS)
Licensee: Nuclear Management Company, LLC
Facility: Point Beach Nuclear Plant
Location: 6610 Nuclear Road
Two Rivers, WI 54241
Dates: January 14 through 18, 2002
Inspectors: Robert C. Daley, Reactor Inspector
George M. Hausman, Senior Reactor Inspector (Lead)
Kenneth G. OBrien, Senior Reactor Inspector
Darrell L. Schrum, Reactor Inspector
Observer: Nicholas A. Valos, Reactor Inspector (Trainee)
Approved by: Ronald N. Gardner, Chief
Electrical Engineering Branch
Division of Reactor Safety
SUMMARY OF FINDINGS
50-266/02-002(DRS); 50-301/02-002(DRS), on 01/14-18/2002, Nuclear Management
Company, LLC, Point Beach Nuclear Plant. Evaluations of Changes, Tests, or Experiments
and Permanent Plant Modifications Report.
The report covers a five day announced inspection. The inspection was conducted by four
Region III based reactor inspectors and one observer in training. No findings of significance
were identified. The significance of most findings is indicated by their color (Green, White,
Yellow, Red) using IMC 0609 Significance Determination Process (SDP). 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.
Findings for which the SDP does not apply are indicated by No Color or by the severity level of
the applicable violations.
A. Inspector Identified Findings
Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity
No findings of significance were identified.
2
Report Details
Summary of Plant Status
Units 1 and 2 were operated at or near 100 percent power throughout the inspection period.
1. REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R02 Evaluations of Changes, Tests, or Experiments (71111.02)
.1 Review of 10 CFR 50.59 Evaluations and Screenings for Changes, Tests, or
Experiments
a. Inspection Scope
The inspectors reviewed ten evaluations performed pursuant to 10 CFR 50.59. The
evaluations related to permanent plant modifications, setpoint changes, procedure
changes, conditions adverse to quality, and changes to the updated final safety analysis
report. The inspectors reviewed the evaluations to verify that the evaluations were
thorough and that prior NRC approval was obtained as appropriate. The inspectors also
reviewed fifteen screenings where the licensee had determined that a 10 CFR 50.59
evaluation was not necessary. In regard to the changes reviewed where no 10 CFR
50.59 evaluation was performed, the inspectors verified that the changes did not meet
the threshold to require a 10 CFR 50.59 evaluation. These evaluations and screenings
were chosen based on risk significance of samples from the different cornerstones.
b. Findings
No findings of significance were identified.
1R17 Permanent Plant Modifications (71111.17)
.1 Review of Recent Permanent Plant Modifications
a. Inspection Scope
The inspectors reviewed ten permanent plant modifications that were installed in the last
two years. The modifications were chosen based upon their affecting systems that had
high probabilistic risk analysis (PRA) significance in the licensee's Individual Plant
Evaluation (IPE) or high maintenance rule safety significance. The inspectors reviewed
the modifications to verify that the completed design changes were in accordance with
the specified design requirements and the licensing bases and to confirm that the
changes did not affect any systems' safety function. Design and post-modification
testing aspects were reviewed to ensure the functionality of the modification, its
3
associated system, and any support systems. The inspectors also reviewed the
modifications performed to verify the modification did not place the plant in an increased
risk configuration.
b. Findings
No findings of significance were identified.
4. OTHER ACTIVITIES (OA)
4OA2 Identification and Resolution of Problems
a. Inspection Scope
The inspectors reviewed a selected sample of corrective action documents associated
with the licensees permanent plant modifications and concerning 10 CFR 50.59
evaluations and screenings to verify that the licensee had an appropriate threshold for
identifying issues. The inspectors evaluated the effectiveness of the corrective actions
for the identified issues.
b. Findings
No findings of significance were identified.
4OA6 Meetings
Exit Meeting
The inspectors presented the inspection results to Mr. Taylor and other members of
licensee management at the conclusion of the inspection on January 18, 2002. The
licensee acknowledged the findings presented. No proprietary information was
identified.
4
KEY POINTS OF CONTACT
Nuclear Management Company, LLC
J. Anderson, Production Planning Manager
L. Armstrong, Design Engineering Manager
D. Black, Nuclear Safety Engineer
D. Carter, Seismic Qualification Engineer
A. Cayia, Site Operations Director
D. Dobson, IST Engineer
C. Drescher, Modification Engineer
J. Ertman, NMC Fleet Fire Protection Eng
F. Flentje, Licensing Specialist
N. Hoefert, Programs Engineering Manager
J. Hanna, System Engineer
R. Hornak, Supervising Engine
R. Hannemann, Supervising Engineer
D. Hettick, Performance Improvement Manager
K. Holt, Supervising Engineer
V. Kaminskas, Maintenance Manager
T. Kendall, Supervising Engineer
A. Little, System Engineer
J. Marean, Engineering Drafting Supervisor
J. MacNamara, Supervising Engineer
R. Mende, KPB Engineering Director
D. Pederson, System Engineer
L. Peterson, Engineering Processes Manager
K. Peveler, Nuclear Oversight Manager
R. Repshas, KPB Site Services Manager
J. Roberts, MOV Engineer
M. Rosseau, Supervising Engineer
D. Schoon, Operations Manager
T. Taylor, Plant Manager
S. Thomas, Radiation Protection Manager
T. Vandenbosch, AOP Coordinator
NRC
P. Krohn, Senior Resident Inspector
5
LIST OF ACRONYMS USED
ADAMS Agencywide Documents Access and Management System
ANSI American National Standards Institute
AOP Abnormal Operating Procedure
ATWS Anticipated Transient Without Scram
CCW Component Cooling Water
CFR Code of Federal Regulations
dc Direct Current
DPR Demonstration Power Reactor
DRS Division of Reactor Safety
ECR Engineering Change Request
EDG Emergency Diesel Generator
EOP Emergency Operating Procedure
EQ Environmental Qualification
ESFAS Engineered Safety Features Actuation System
F Fahrenheit
FSAR Final Safety Analysis Report
GL Generic Letter
gov Government
html Hypertext Markup Language
http Hypertext Transfer Protocol
HVAC Heating Ventilation and Air Conditioning
HX Heat Exchanger
IA Instrument Air
IMC Inspection Manual Chapter
IPE Individual Plant Evaluation
IR Inspection Report
IST In-service Testing
KPB Kewaunee and Point Beach
LLC Limited Liability Company
LOV Loss of Voltage
MCC Motor Control Center
MOV Motor Operated Valve
NEI Nuclear Energy Institute
NMC Nuclear Management Company
NRC United States Nuclear Regulatory Commission
NRR Office of Nuclear Reactor Regulation
OA Other Activities
PARS Publicly Available Records
PBNP Point Beach Nuclear Plant
PRA Probabilistic Risk Analysis
QA Quality Assurance
QC Quality Control
6
LIST OF ACRONYMS USED
RG Regulatory Guide
RCP Reactor Coolant Pump
RWST Refueling Water Storage Tank
SD Shutdown
SDP Significance Determination Process
SE Safety Evaluation
SER Safety Evaluation Report
SFP Spent Fuel Pool
SI Safety Injection
SSFI Safety Systems Functional Inspection
TDAFW Turbine Driven Auxiliary Feedwater
TRM Technical Requirements Manual
TS Technical Specification
USAR Updated Safety Analysis Report
USI Unresolved Safety Issue
V Volt
wpd WordPerfect Document
www World Wide Web
7
LIST OF DOCUMENTS REVIEWED
The following is a list of licensee documents reviewed during the inspection, including
documents prepared by others for the licensee. Inclusion on this list does not imply that NRC
inspectors reviewed the documents in their entirety, but rather that selected sections or portions
of the documents were evaluated as part of the overall inspection effort. Inclusion of a
document in this list does not imply NRC acceptance of the document, unless specifically stated
in the inspection report.
CALCULATIONS
Number Description Rev/Date
692301-2.2 Effect of Loss of Ventilation on Critical Plant Areas at the 2
PBNP Following a Station Blackout
99-0031 Structural Qualification of D-07 and D-08 Seismic Brace 0
99-0117 Evaluate Temporary 8 Inch SW Discharge from CCW HX 1
Bechtel Primary Auxiliary Building Ventilation Calculation February 16, 1970
- 6118
N93-060 WE - PBNP Battery D305 DC System Calculation 1
N94-056 SFP HX 013A/B - SW Flow vs Temperature Requirement 2
N94-130 4160V and 480V Safeguards Buses LOV Relay Setpoints 1
N-94-158 Verification of Required AFW Pump Differential Head for November 15, 1994
Accident Flow Rate
M-09334.212- Turbine Driven AFW Low Pressure Capability July 10, 1997
AF.1
M-09334.425- Evaluation of Impact of Check Valve AF-100/AF-101 0
AF.1 Replacement
WE 0005-10 Determination of Time Available to Isolate the RWST 0
WE 300060 Piping System Qualification Report, Service Water Piping 1
WE 300068 Piping System Qualification Report - Service Water Piping, 0
Return from HX-13A and HX-13B
CONDITION REPORTS (CRs) GENERATED DURING INSPECTION
Number Description Rev/Date
CAP001871 QA Calculation Cannot Be Found in Controlled Records January 15, 2002
CAP001877 FSAR Discrepancy on Definition of RG 1.97 Category 2 January 16, 2002
CAP001886 Incomplete 10 CFR 50.59 Screening Answer for Changes January 16, 2002
to Relief Valve CC-736A/B
CAP001897 Letdown Isolation Valve Appendix R Operation During January 17, 2002
Degraded Voltage Conditions
CAP001900 Incomplete Corrective Actions Regarding Classification of January 17, 2002
RC-427
CAP001901 FSAR Chapter 9 Changes for CFC Service Water January 17, 2002
Pressure Not Also Made in Chapter 6
CAP001910 Safety Evaluation 2000-0014 Incomplete January 17, 2002
8
CONDITION REPORTS (CRs) GENERATED DURING INSPECTION
Number Description Rev/Date
CAP001915 Questioning Corrective Action for CR00-2859 on January 18, 2002
Screening Procedure Temp Change
CAP001916 Incorrect Answer to Tech Spec Change Question in January 18, 2002
10 CFR 50.59 Evaluation
CAP003518 IT-21/22 Needs Procedural Tie January 16, 2002
CONDITION REPORTS (CRs) GENERATED PRIOR TO INSPECTION
Number Description Rev/Date
96-1631 Unanticipated Alarm on G-03 During Start June 28, 1997
97-0174 Incorrect SW System Design Pressure Stated in DG-M-03 January 20, 1997
97-1089 Momentary Air Bank Pressure Low Alarm Received April 5, 1997
When G03 EDG Started for Performance of TS-83
99-1618 Concern IDd with SW System Operating Pressure September 24, 1999
During Design Basis Accident with Only 1 Unit in Operation
00-0128 P32 Thermocouple Installation Not Documented January 11, 2000
00-0204 Inappropriate Use of Pre-Screening Criteria January 20, 2000
00-1155 Less Than Adequate 10 CFR 50.59's April 7, 2000
00-2841 Abnormal Operating Procedure 6E Concerns September 22, 2000
00-2859 Installation of Temporary Gauge for AFW Pump Causes September 27, 2000
Potential to Violate Technical Specifications
01-1221 Procedures Incorrectly Exempted from 10 CFR 50.59 April 11, 2001
Screening
01-0403 Inadequate Safety Screening February 8, 2001
DRAWINGS
Number Description Rev/Date
Enertech Nozzle Check Valve, 3, Class 600 DRV-Z 3
PD99532
EMD8413730, Schematic Diagram Diesel Generator G01 Start No. 1 December 11, 2001
Sh. 3 Circuitry
EMD8413730, Schematic Diagram Diesel Generator G01 Start No. 2 December 11, 2001
Sh. 4 Circuitry
EMD8413730, Schematic Diagram Diesel Generator G01 Annunciator November 13, 2001
Sh. 6 Part-2
MFWK Feed Water System 38
00000138
MAFK Auxiliary Feed Water System 69
00000169
ENGINEERING CHANGE REQUESTS (ECRs)
Number Description Rev/Date
1999-0186 MR 98-024*B October 26, 1999
9
ENGINEERING CHANGE REQUESTS (ECRs)
Number Description Rev/Date
2000-0016 MR 98-024*B March 16, 2000
2000-0020 MR 98-024*E March 28, 2000
2000-0023 MR 98-024*B September 18, 2000
2000-0024 MR 98-024*B September 14, 2000
2000-0025 MR 98-024*B September 11, 2000
2000-0026 MR 98-024*B September 18, 2000
2000-0030 MR 98-024*E April 4, 2000
2000-0032 MR 98-024*B September 18, 2000
2000-0033 MR 98-024*B September 18, 2000
2000-0034 MR 98-024*E May 30, 2000
2000-0036 MR 98-024*E August 22, 2000
2000-0038 MR 98-024*E August 22, 2000
2000-0039 MR 98-024*E April 11, 2000
2000-0040 MR 98-024*E May 31, 2000
2000-0041 MR 98-024*E April 5, 2000
2000-0042 MR 98-024*E May 3, 2000
2000-0043 MR 98-024*E April 6, 2000
2000-0044 MR 98-024*B September 14, 2000
2000-0046 MR 98-024*E April 7, 2000
2000-0047 MR 98-024*E April 11, 2000
2000-0049 MR 98-024*E April 8, 2000
2000-0050 MR 98-024*E April 10, 2000
2000-0052 MR 98-024*E April 10, 2000
2000-0054 MR 98-024*E April 12, 2000
2000-0056 MR 98-024*E April 26, 2000
2000-0060 MR 98-024*E April 20, 2000
2000-0061 MR 98-024*E April 26, 2000
2000-0063 MR 98-024*E May 23, 2000
2000-0064 MR 98-024*E April 28, 2000
2000-0066 MR 98-024*E May 3, 2000
2000-0078 MR 98-024*E June 1, 2000
2000-0085 MR 98-024*E June 14, 2000
2000-0093 MR 98-024*E June 14, 2000
2000-0094 MR 98-024*E June 14, 2000
2000-0101 MR 98-024*E June 19, 2000
2000-0108 MR 98-024*E June 29, 2000
2000-0109 MR 98-024*E July 4, 2000
2000-0112 MR 98-024*E July 10, 2000
2000-0117 MR 98-024*E July 8, 2000
2000-0128 MR 98-024*B September 18, 2000
2000-0135 MR 98-024*B September 11, 2000
2000-0137 MR 98-024*B September 11, 2000
10
ENGINEERING CHANGE REQUESTS (ECRs)
Number Description Rev/Date
2000-0141 MR 98-024*B September 13, 2000
2000-0156 MR 98-024*E August 11, 2000
2000-0157 MR 98-024*B October 3, 2000
2000-0158 MR 98-024*B September 18, 2000
2000-0161 MR 98-024*B September 18, 2000
2000-0165 MR 98-024*B September 14, 2000
2000-0174 MR 98-024*B October 4, 2000
2000-0204 MR 98-024*E October 26, 2000
2001-0017 MR 98-024*E February 14, 2001
2001-0027 MR 98-024*E February 27, 2001
MODIFICATIONS:
Number Description Rev/Date
MR 94-048 Seismic Modifications of 1A-05, 2A-05, D-07, and D-08 February 10, 1999
MR 97-129*A U1 Replace Check Valves AF-100 and AF-101 With a May 27, 1999
New Style
MR 98-024*B U0 Spent Fuel Pool Cooling Service Water Alternate April 28, 1999
Supply/ Return Lines
MR 98-024*E U0 Service Water From Component Cooling Water Heat January 10, 2000
Exchanger Return Header Piping/Isolation
MR 98-047 U1 Pressurizer Level Controller Upgrade April 13, 1998
MR 99-005*C Instrument Air Containment Isolation Valve Trim Package June 17, 1999
Replacement
MR 99-0055 Instrument Air Containment Isolation Valve Logic Change February 17, 2000
MR 99-029*A AFW Pump P-38A Minimum Flow Re-circulation Line January 28, 2000
Orifice
MR 00-051 RWST (T-013) Vent Upgrade - Unit 1 June 12, 2000
MR 00-070 Elimination of Nuisance Low Starting Air Pressure Alarms May 21, 2001
During EDG Start of G01
PROCEDURES
Number Description Rev/Date
AOP-6E Alternate Boration/Loss of Shutdown Margin 8&9
AOP-6F Low Concentration Water Pockets in RCS 2
AOP-6H Quadrant Power Tilt 0
AOP-27 Recovery from Inadvertent Containment Isolation (Unit 2) 0
CSP-H.1 U2 Response to Loss of Secondary Heat Sink 22
CSP-S.1 Response to Nuclear Power Generator ATWS 22
EOP-0.1 Reactor Trip Response - Unit 2 25
EOP-1.1 Safety Injection Termination (Unit 2) 28
EOP-1.3 Transfer to Containment Sump Re-circulation Unit 2 26
11
PROCEDURES
Number Description Rev/Date
IT-08A Cold Start of TDAFW Pump and Valve Test (Quarterly) 25
Unit 1
IT-10 Test of Electrically-Driven AFWPs and Valves (Quarterly) 43
IT-10 Temporary Change 2000-0463 39
IT-110 Instrument Air Valves (Quarterly) Unit 1 16
IT-115 Instrument Air Valves (Quarterly) Unit 2 15
IT-305B Steam Generator B Main Feed Line Check Valves 7
(Cold SD) Unit 2
IT-350 SI Check Valves (Cold Shutdown) 2
IWP96-071* EDG G01 Governor Replacement Post-Modification 0
A2 Testing
NP1.1.2 Procedure and Administrative Controls 4
NP1.1.3 Procedure Preparation Review and Approval 14
NP1.1.4 Use and Adherence of Procedures and Work Plans 6
NP5.1.8 10CFR50.59/72.48 Applicability, Screening and Evaluation 1
NP7.2.1 Plant Modifications 8
NP10.3.1 Authorization of Changes, Tests, and Experiments 14
OM3.7 AOP and EOP Procedure Sets Use and Adherence 10
ORT47 IA Supply Unit 1 17
ORT47 IA Supply Unit 2 14
ORT48 IA Supply Unit 1 16
ORT48 IA Supply Unit 2 12
1ICP02.003- RPS Logic Train A Monthly Surveillance Test 11 & 12
A-1
1ICP02.003- RPS Logic Train B Monthly Surveillance Test 12 & 13
B-1
1SOP-CC-001Component Cooling System 6&7
REFERENCES
Number Description Rev/Date
EWR 97-159 Determine Replacement Check Valve Design for December 16, 1997
AF-100/101
DBD-02 CCW System Design Basis Document 0
DBD-29 Auxiliary Building and Control Building HVAC 0
FSAR Chapters 6 and 9 June 2001
Letter NRC SER on Resolution of USI A-46 at PBNP July 7, 1998
Letter Conformance to RG 1.97 for PBNP July 11, 1986
Memo Hannemann to OBrien, Follow-Up on Plant Walkdown of January 17, 2002
PAB Ventilation System,
2000-026 Managers Supervisory Staff Meeting Minutes May 2, 2000
NPM 99-0864 Seismic Evaluation of Auxiliary Bldg HVAC System July 29, 1999
12
REFERENCES
Number Description Rev/Date
NPM 99-1099 Downgrading Seismic Classification of FW Regulating & September 28,
Bypass Valves 1999
PBF-2031 Auxiliary Building Shift Log 43
PBF-2031 Daily Logsheet 56
RG 1.97 Instrumentation For Light-Water-Cooled Nuclear Power December 1, 1980
Plants To Assess Plant And Environs Conditions During
And Following An Accident - Revision 2
SPEED Set Point, Drawing Number, and Capacity Change for November 8, 2000
2000-131 CC-736A Spare Parts Equivalency Document
50.59 EVALUATIONS(SEs)
Number Description Rev/Date
99-0075-02 Instrument Air Containment Isolation Valve Trim Pack March 22, 2000
Replacement
2000-0014 Downgrade the Seismic Design Classification of Auxiliary February 16, 2000
Building Ventilation and MFW Equipment That Isolates
the Supply of MFW to the Steam Generators in FSAR
2000-0022-01 Chapter 8, DG Systems FSAR Changes 0
2000-0023-01 FSAR Phase II Review and Upgrade Project, Section 9.6 August 30, 2000
2000-0044 Refueling Water Storage Tank (RWST) Seismic Upgrade April 4, 2000
2000-0052 MR 98-024*V - Modify SI Logic for Non-Essential SW May 3, 2000
Load Isolation Valves
2000-0055 AFW Pump P-38A and P-38B Minimum Flow Recirculating May 10, 2000
Line Flow Orifice Replacement
2000-0063 MR 97-014*E, Transfer dc Supplies for Inverters 1DY-01 June 20, 2000
and 2DY-02, Install Panel D-26 and Transfer Loads to
D-26
2000-0077 Changes to SW System Operating Procedures and FSAR August 9, 2000
2000-0093 Revise Procedure for Spurious Operation of SI 851 A/B September 21, 2000
Valves
2001-0007 CCW System Closed Loop Inside Containment 0
2001-0014 MR 98-024*J - Unit 1 Containment Fan Cooler and Fan March 14, 2001
Motor Cooler Replacement
2001-0027 MR 00-103, SW Upgrades to EDG, G02 June 6, 2001
2001-0057 TRM 3.5.1/TSR 3.5.1.3 & TSR 3.5.1.3 Bases October 16, 2001
(Draft Rev. C)
2001-0216 Filling RHR Common Suction From RWST With P-33 April 3, 2001
50.59 SCREENS(SCRs)
Number Description Rev/Date
1999-0430 Replace 3" AFW Check Valves 1AF-0100 and 1AF-0101 May 28, 1999
13
50.59 SCREENS(SCRs)
Number Description Rev/Date
2000-0023 RMP 9200-6, Switchyard Battery D-800, D-801, and 0
D-807 Capacity Test
2000-0062 Changes to PBNP 6/99 FSAR Section 8.6 120Vac Vital January 28, 2000
Instrument Power (Y)
2000-0072 Changes to PBNP June 99 FSAR Section 7.2, RPS, 7.3, February 3, 2000
ESFAS, and 7.6.1, Nuclear Instrumentation System
2000-0100 1-SOP-CC-001, Component Cooling System, Revision 2, February 9, 2000
2-SOP-CC-001, Component Cooling System, Revision 3,
PBF 2031, Auxiliary Building Shift Log, Revision 43
2000-0207 Revise TLB-59 (Tank Level Book, Diesel Generator March 6, 2000
G-03/G-04 Day Tank T-176A/B)
2000-0401 Temporary Ventilation for Main Feed Pump Motors May 8, 2000
2000-0695 Replacement Valve and Setpoint Change for Unit 1 & 2 September 7, 2000
CC-736A/B
2000-0783 50.59 Screening, AF Vent & Drain Temporary Gauges September 14, 2000
2000-0975 Relief Valve Capacity Change for Unit 2 CC-736A October 28, 2000
2001-0053 Temporary Changes to EDG G-03 Temperature and January 19, 2001
Alarm Functions
2001-0067 Downgrade CCW Heat Exchanger SW Relief Valves January 31, 2001
From Safety Related to Augmented Quality
2001-0084 Service Water System Malfunction January 26, 2001
2001-0141 Revise RMP 9367, Containment Coatings to Include February 16, 2001
Lenience on Dry Film Thickness Range for Carboguard
890
2001-0205 AOP 27, Recovery from Inadvertent Containment March 6, 2001
Isolation
2001-0208 ORT 69, Revision 21, CCW To and From 1P-1B March 6, 2001
Refueling Shutdown Unit 1
2001-0216 Filling RHR Common Suction From RWST With P-33 April 3, 2001
14
LIST OF INFORMATION REQUESTED
INITIAL DOCUMENT REQUEST
(Sent to Licensee on December 18, 2001)
Inspection Report: 50-266/02-002(DRS); 50-301/02-002(DRS)
Inspection Dates: January 14 -18, 2002
Inspection Procedures: IP 71111.02, Evaluations of Changes, Tests, or Experiments
IP 71111.17, Permanent Plant Modifications
Lead Inspector: George M. Hausman, (630) 829-9743
I. Information Needed for In-Office Preparation Week
The following information is needed by January 7, 2002, or sooner, to facilitate the
selection of specific items that will be reviewed during the on-site inspection week. The
team will select specific items from the information requested below and submit a list to
your staff by January 10, 2002. We request that the specific items selected from the
lists be available and ready for review on the first day of inspection. If you have any
questions regarding this information, please call the team leader as soon as possible.
All lists requested should cover a two year span. All information should be sent
electronically (as a PDF or WordPerfect/Word document) if at all possible.
a. List of permanent plant modifications to risk significant systems, structures, or
components. For the purpose of this inspection, permanent plant modifications
include permanent: (i) plant changes, (ii) design changes, (iii) set point changes,
(iv) procedure changes, (v) equivalency evaluations, (vi) suitability analyses,
(vii) calculations, and (viii) commercial grade dedications.
b. List of all 10 CFR 50.59 completed evaluations involving: (i) changes to facility
(modifications), (ii) procedure revisions, (iii) tests or non-routine operating
configurations, (iv) changes to the UFSAR, and (v) calculations.
c. List of all 10 CFR 50.59 screenings for changes that have been screened out as
not requiring a full evaluation involving: (i) changes to facility (modifications),
(ii) procedure revisions, (iii) tests or non-routine operating configurations,
(iv) changes to the UFSAR, and (v) calculations.
d. List of all 10 CFR 50.59 validations or applicability reviews done in lieu of a full
10 CFR 50.59 evaluation.
e. List of corrective action documents (open and closed) that address the plant
permanent modification process and 10 CFR 50.59 issues or concerns.
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LIST OF INFORMATION REQUESTED
f. List of special tests or experiments and non-routine operating configurations.
g. Copies of modification procedure(s), post-modification testing procedure(s) and
10 CFR 50.59 procedures.
h. Name(s) and phone numbers for the regulatory and technical contacts.
i. Latest Organizational Chart.
II. Information to be Available on First Day of Inspection (January 14, 2002)
a. Copies of all selected items need to be ready for the inspectors when they arrive
on-site. Selected items will be relayed to the NRC coordinator/contact person by
January 10th.
b. The following information needs to be available to the team once they arrive
on-site. Copies of these documents do not need to be solely available to the
team as long as the inspectors have easy and unrestrained access to them.
- Technical Specifications
- Latest IPE/PRA Report
- Vendor Manuals
- The Latest 10 CFR 50.59 FSAR Update Submittal
c. Please ensure that all supporting documents for the selected items have been
located and are readily retrievable as the team will likely be requesting these
documents during the inspections. Examples of supporting documents are:
- Calculations supporting the selected modifications or 10 CFR 50.59
evaluations
- Post-modification tests for the selected modifications
- Copies of other evaluations or validations referred to by a modification or
10 CFR 50.59 evaluation.
- Drawings supporting the modifications.
- Procedures affected by the modifications.
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LIST OF INFORMATION REQUESTED
- UFSAR change papers generated due to a 10 CFR 50.59 evaluation.
III. Information to Be Provided Throughout the Inspection
a. Copies of any Condition Report generated as a result of the teams questions or
queries during this inspection.
b. Copies of the list of questions submitted by the team members and the
status/resolution of the information requested (provided daily during the
inspection to each team member).
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LIST OF INFORMATION REQUESTED
SPECIFIC DOCUMENTS REQUESTED
(Sent to Licensee on or about January 8, 2002)
Inspection Report: 50-266/02-002(DRS); 50-301/02-002(DRS)
Inspection Dates: January 14 -18, 2002
MODIFICATIONS:
Number Description
94-048 Seismic Modifications of 1A-05, 2A-05, D-07, and D-08
95-048 U1 EDG Output Breaker Under Voltage Permissive Time Delay
96-022 U0 125 VDC Reconfiguration
96-081A U1 - Instrument Bus Transfer Switch Installation
97-073A U1 Add Motor Operators to SI-857A(B) Valves - Electrical
97-073C Conversion of SI-897A and SI-897B to Fail Open Actuators From Fail Closed
Actuators - Electrical
97-081A U0 Add 2 Motor Operators to Service Water to Spent Fuel Pool Cooling Heat
Exchanger Isolation Valves - Manual Only (Part 1 of 3)
97-129A U1 Replace Check Valves AF-100 and AF-101 With a New Style
98-024B U0 Spent Fuel Pool Cooling Service Water Alternate Supply / Return Lines
98-024E U0 Service Water From Component Cooling Water Heat Exchanger Return
Header Piping / Isolation
98-024U Modify The Safety Injection Signals to the Service Water Non-essential Load
Isolation Valves Installed Under the *H and *I Packages
98-024W Disable Unit 2 Four-Out-Of-Six Service Water Isolation Logic
98-045A U1 Replace RPI Electronics and Associated Components Install Cable from
98-047 U1 Pressurizer Level Controller Upgrade
99-005G Instrument Air Containment Isolation Valve Logic Change
99-019 Facade Freeze Protection Upgrades
99-029A Auxiliary Feedwater Pump P-38A Minimum Flow Recirculation Line Orifice
00-051 Refueling Water Storage Tank (T-013) Vent Upgrade - Unit 1
00-070 Elimination of Nuisance Low Starting Air Pressure Alarms During EDG Start -
G01
01-021 Replace 1RC-427 Motor Operated Valve Actuator Motor
01-040 Replace P-32C Motor
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LIST OF INFORMATION REQUESTED
50.59 EVALUATIONS
Number Description
SE 2000-0012 MR 98-024E, Component Cooling Water Heat Exchangers Service Water
Alternate Return
SE 2000-0014 Downgrade The Seismic Design Classification of Auxiliary Building
Ventilation
SE 2000-0022 Changes to PBNP 6/99 FSAR Section 8.8 Diesel Generator (DG) System
SE 2000-0022-01 Changes to PBNP 6/99 FSAR Section 8.8 Diesel Generator (DG) System
SE 2000-0023 FSAR Phase II Review and Upgrade Project - Section 9.6 Service Water
SE 2000-0023-01 FSAR Phase II Review and Upgrade Project - Section 9.6 Service Water
SE 2000-0025 Freeze Seal to Support 1SI-00853C Disassembly
SE 2000-0044 Refueling Water Storage Tanks (RWST) Seismic Upgrade
SE 2000-0052 MR 98-024V Modify SI Logic for Non-Essential Service Water Load Isolation
Valves
SE 2000-0063 MR 97-014E Transfer DC Supplies for Inverters 1DY-01 and 2DY-02, Install
Panel D-26
SE 2000-0067 Re-Route U2 Steam Generator Pressure Transmitter 2 PT-483 Cable
SE 2000-0077 Changes to Service Water Operating Procedures and FSAR
SE 2000-0077-01 Changes to Service Water Operating Procedures and FSAR
SE 2000-0093 Revise Procedures for Spurious Operation of SI-851A/B Valves
SE 2000-0100 Temporary Modification For Containment Penetration Number 56 Unit 2
SE 2000-0124 Revision of Technical Information in FSAR Section 6.5 Leakage Detection
SE 2000-0124-01 Revision of Technical Information in FSAR Section 6.5 Leakage Detection
SE 2000-0129 Revision of Technical Information in FSAR Section 11.5 Radiation Monitoring
System
SE 2001-0007 Component Cooling Water Closed Loop Inside Containment
SE 2001-0010 Temporary Power for Motor Control Center 1B-31 and 1B-32
SE 2001-0014 MR 98-024J, Unit 1 Containment Fan Cooler and Fan Motor Cooler
Replacement
SE 2000-0027 MR 00-103 Service Water Upgrades to Emergency Diesel Generator G-02
SE 2001-0029 Temporary Seal Water Supply to P-134, TM 01-025
SE 2001-0034 MR 01-052 Steam Generator Blowdown Isolation Modification
SE 2001-0034-01 MR 01-052 Steam Generator Blowdown Isolation Modification
SE 2001-0040 Downgrade Component Cooling Water Heat Exchanger Service Water Valve
SE 2001-0057 TRM 3.5.1/TSR 3.5.1.3 and TSR 3.5.1.3 Bases Revision (Draft Rev. C)
SE 2001-0059 Operation of the Auxiliary Feedwater Pumps Without Cooling Water
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LIST OF INFORMATION REQUESTED
50.59 SCREENS
Number Description
SCR 2000-0023 RMP 9200-6 Switchyard Battery D-800, D-801, and D-807 Capacity Test
Revision 0
SCR 2000-0062 Changes to PBNP 6/99 FSAR Section 8.5 480 Vac Electrical Distribution
System
SCR 2000-0063 Changes to PBNP 6/99 FSAR Section 8.6 120 Vac Vital Instrument Power (Y)
SCR 2000-0072 Changes to PBNP 6/99 FSAR Section 7.2 Reactor Protection System, 7.3
Engineered Safety Systems
SCR 2000-0100 1-SOP-CC-001 Component Cooling System, Revision 2, 2-SOP-CC-001,
Revision 3, and PBF-2031
SCR 2000-0207 Revise TLB-59 (Tank Level Book, Diesel Generator G-03/G-04 Day Tank T-
176A/B)
SCR 2000-359 Engineered Safety Features System Logic Surveillance Testing Revision 0
Procedures
SCR 2000-0401 Temporary Ventilation for Main Feed Pump Motors
SCR 2000-0975 Relief Valve Capacity Change for Unit 2 CC 736A
SCR 2000-1120 Tcn 2000-0752 OP-4A Filling and Venting Reactor Coolant System
SCR 2000-1156 Unit 1 and 2 AOP-2C Auxiliary Feed Pump Steam Binding or Overheating,
Revision 5
SCR 2001-0053 EDG G-03 Temporary Modification 01-002 and 01-003 for Temporary
Changes to Temperature Indication
SCR 2001-0063 Revision to Operations Procedure OI 106 Facade Freeze Protection
SCR 2001-0067 Downgrade Component Cooling Water Heat Exchanger Service Water Relief
Valves
SCR 2001-0070 Reactor Protection System Logic Testing Procedure Revision
SCR 2001-0084 Service Water System Malfunction
SCR 2001-0087 Emergency Diesel Generator G-01 Monthly
SCR 2001-0094 Speed 2001-003 Replacement of Amoco American Industrial Oil ISO 100 with
Mobil 1 TRI-SY
SCR 2001-0116 Temporary Modification 2001-008
SCR 2001-0140 OI 151 HX-012C and D Component Cooling System Heat Exchanger Data
Collection, Revision 2
SCR 2001-0141 Revise RMP 9367 Containment Coatings to Include Lenience on Dry Film
Thickness Range
SCR 2001-0147 Changes to OP-8a Spent Fuel Pool Cooling Water System, IT-11, Spent Fuel
Pool Cooling
SCR 2001-0176 IT 305B Steam Generator B Main Feed Line Check Valves (Cold Shutdown)
Unit 2
SCR 2001-0189 Reactor Protection and Safeguards Analog Channel Calibration Procedures,
Revision 1
SCR 2001-0205 AOP 27 Recovery from Inadvertent Containment Isolation, Unit 1, Revision 0
SCR 2001-0207 Unit 1 and 2 AOP-9B, Component Cooling System Malfunction, Revision 15/16
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LIST OF INFORMATION REQUESTED
50.59 SCREENS
Number Description
SCR 2001-0208 ORT 69, Revision 21, Component Cooling Water to and from 1P-1B Refueling
Shutdown Unit 1
SCR 2001-0214 Set Point Document 14.2 Changes
SCR 2001-0216 Filling RHR Common Suction from RWST with P-33
SCR 2001-0243 Changes to Containment Spray Pump Test Procedures
SCR 2001-0256 In Progress MR 01-043, Installation of Monitoring Computer for Facade Freeze
Protection
SCR 2001-0260 Revise Sequence of Events for Fill and Vent RHR System
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