ML032400268

IR 05000266-04-001, 05000301-04-001, Point Beach Nuclear Plant, Mid-Cycle Assessment Letter

ML032400268
Person / Time
Site:	Point Beach
Issue date:	08/27/2003
From:	Dyer J NRC/RGN-III
To:	Cayia A Nuclear Management Co
References
IR-04-001
Download: ML032400268 (8)

See also: IR 05000266/2004001

Text

August 27, 2003

Mr. Alfred J. Cayia

Site-Vice President

Point Beach Nuclear Plant

Nuclear Management Company, LLC

6610 Nuclear Road

Two Rivers, WI 54241-9516

SUBJECT: MID-CYCLE ASSESSMENT LETTER - POINT BEACH NUCLEAR PLANT

(REPORT 50-266/04-01; 50-301/04-01)

Dear Mr. Cayia:

On July 30, 2003, the NRC staff completed its mid-cycle plant performance assessment of the

Point Beach Nuclear Plant. The mid-cycle review for Point Beach Nuclear Plant involved the

participation of all technical divisions in evaluating performance indicators (PIs) for the most

recent quarter and inspection results for the first half of the current assessment cycle,

January 1 - December 31, 2003. The purpose of this letter is to inform you of our assessment

of your safety performance during this period and our plans for future inspections at your facility

so that you will have an opportunity to prepare for these inspections and to inform us of any

planned inspections that may conflict with your plant activities.

Plant performance for the most recent quarter was within the Multiple/Repetitive Degraded

Cornerstone column of the NRCs Action Matrix based on a final Red finding in the mitigating

systems cornerstone. Additionally, we have identified a preliminary Red finding associated with

the potential common mode failure of the four auxiliary feedwater (AFW) pumps due to

plugging of the recirculation line pressure reducing orifices. A Regulatory Conference to

discuss the preliminary Red finding was completed on June 6, 2003. Our deliberations on the

significance of this preliminary finding continue, in accordance with NRC Inspection Manual

Chapter (IMC) 0609, Significance Determination Process.

As a result of the final Red finding and the discussion at the annual Agency Action Review

Meeting (AARM) on April 22, 2003, we are currently conducting inspection activities to

accomplish Inspection Procedure (IP) 95003, Supplemental Inspection for Repetitive Degraded

Cornerstones, Multiple Degraded Cornerstones, Multiple Yellow Inputs, or One Red Input. The

IP 95003 inspection began on July 28, 2003, and will be conducted in addition to the baseline

inspections currently scheduled. The intent of IP 95003 is to allow the NRC to obtain a

comprehensive understanding of the depth and breadth of safety, organizational, and

performance issues at facilities where data indicates the potential for serious performance

degradation. The objectives of this inspection are to: (1) provide additional information to be

used in deciding whether the continued operation of the facility is acceptable and whether

additional regulatory actions are necessary to arrest declining performance; (2) provide an

independent assessment of the extent of risk significant issues to aid in the determination of

whether an acceptable margin of safety exists; (3) independently evaluate the adequacy of your

A. Cayia -2-

programs and processes used to identify, evaluate, and correct performance issues;

(4) independently evaluate the adequacy of programs and processes in the affected strategic

performance areas; and (5) provide insight into the overall root and contributing causes of

identified performance deficiencies.

As prescribed by IP 95003, the scope of ongoing NRC inspection activities includes the

assessment of performance in the Reactor Safety Strategic Performance Area, including the

inspection of key attributes such as design, human performance, procedure quality,

configuration control, and emergency response organization readiness. Also, the IP 95003

inspection will review your progress in addressing the substantive cross-cutting issue in the

area of problem identification and resolution.

In addition to the routine NRC inspection and assessment activities, Point Beach performance

is being evaluated quarterly as described in the May 9, 2003, Annual Assessment Follow-Up

Letter - Point Beach Nuclear Plant. Consistent with IMC 0305, plants in the Multiple/Repetitive

Degraded Cornerstone column of the Action Matrix are given consideration at each quarterly

performance assessment review for: (1) declaring plant performance to be unacceptable in

accordance with the guidance in IMC 0305; (2) transferring to the IMC 0350 Oversight of

Operating Reactor Facilities in a Shutdown Condition with Performance Problems process; and

(3) taking additional regulatory actions, as appropriate. On May 22 and July 22, 2003, the NRC

reviewed Point Beach operational performance, inspection findings, and performance indicators

for the first and second quarters of 2003, respectively. During the July 22nd and mid-cycle

reviews of Point Beach performance, we also reviewed recent 3rd quarter events, including the

Unit 2 automatic trip due to a main feed pump failure on July 10, the manual safety injection

signal and reactor trip on July 11, and the Unit 1 automatic trip on July 15 due to failure of a

control rod drive power supply voltage regulator. From our initial review of these recent

operational challenges and their apparent causes, we concluded that Point Beach performance,

while not good, did not represent either significant degradation or unsafe operations. Based on

the quarterly and mid-cycle reviews, we determined that the plant continues to be operated in a

safe manner and that no additional regulatory actions are currently warranted. The NRC will

continue to closely monitor Point Beach performance consistent with the guidance in IMC 0305.

In our Annual Assessment Letter dated March 4, 2003, we advised you of a substantive

cross-cutting issue in the area of Problem Identification and Resolution. During the first two

quarters of this assessment period, the NRC continued to identify issues involving problem

identification and resolution implementation weakness. Specifically, in April 2003, we

determined that your corrective actions to upgrade the safety function of an auxiliary feedwater

system air-operated recirculation valve had failed to ensure that successful operation of the

recirculation line air-operated valve was dependent only on safety-related support systems.

Following the corrective actions, successful operation of the valve was still dependent upon

nonsafety-related power to an interposing relay. Additionally, the corrective actions failed to

discover a single failure mechanism involving a system orifice modification. Our review of your

efforts to address this cross-cutting issue continues through our baseline and IP 95003

inspection activities.

A. Cayia -3-

The enclosed inspection plan details the inspections scheduled through September 30, 2004.

Please note, that, in addition to baseline and ongoing IP 95003 inspections, Temporary

Instruction (TI) TI 2515/150, Reactor Pressure Vessel Head and Vessel Head Penetration

Nozzles Inspection, is scheduled for October 6 - 25, 2003. The enclosed inspection plan is

provided to minimize the resource impact on your staff and to allow for scheduling conflicts and

personnel availability to be resolved in advance of inspector arrival onsite. Routine resident

inspections are not listed due to their ongoing and continuous nature. The inspections in the

last 6 months of the inspection plan are tentative and may be revised at the end-of-cycle review

meeting.

In accordance with 10 CFR 2.790 of the NRCs Rules of Practice, a copy of this letter and its

enclosure will be made 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/reading-rm/adams.html (the Public Electronic Reading Room). If

circumstances arise which cause us to change the inspection plan, we will contact you to

discuss the change as soon as possible. Please contact Mr. Anton Vegel at (630) 829-9620

with any questions you may have regarding this letter or the inspection plan.

Sincerely,

/RA by G. Grant acting for/

J. E. Dyer

Regional Administrator

Docket Nos. 50-266; 50-301

License Nos. DPR-24; DPR-27

Enclosure: Point Beach Inspection/Activity Plan

See Attached Distribution

A. Cayia -3-

The enclosed inspection plan details the inspections scheduled through September 30, 2004.

Please note, that, in addition to baseline and ongoing IP 95003 inspections, Temporary

Instruction (TI) TI 2515/150, Reactor Pressure Vessel Head and Vessel Head Penetration

Nozzles Inspection, is scheduled for October 6 - 25, 2003. The enclosed inspection plan is

provided to minimize the resource impact on your staff and to allow for scheduling conflicts and

personnel availability to be resolved in advance of inspector arrival onsite. Routine resident

inspections are not listed due to their ongoing and continuous nature. The inspections in the

last 6 months of the inspection plan are tentative and may be revised at the end-of-cycle review

meeting.

In accordance with 10 CFR 2.790 of the NRCs Rules of Practice, a copy of this letter and its

enclosure will be made 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/reading-rm/adams.html (the Public Electronic Reading Room). If

circumstances arise which cause us to change the inspection plan, we will contact you to

discuss the change as soon as possible. Please contact Mr. Anton Vegel at (630) 829-9620

with any questions you may have regarding this letter or the inspection plan.

Sincerely,

/RA by G. Grant acting for/

J. E. Dyer

Regional Administrator

Docket Nos. 50-266; 50-301

License Nos. DPR-24; DPR-27

Enclosure: Point Beach Inspection/Activity Plan

See Attached Distribution

DOCUMENT NAME: G:\Branch TSS\midcycle2003\Poi midcycle ltr 03.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 RIII RIII RIII

NAME JCameron/co AVegel GGrant Ggrant for JDyer

DATE 08/15/03 08/18/03 08/26/03 08/27/03

OFFICIAL RECORD COPY

A. Cayia -4-

cc w/encl: R. Grigg, President and Chief

Operating Officer, WEPCo

John Paul Cowan, Chief Nuclear Officer

Licensing Manager

D. Weaver, Nuclear Asset Manager

Joseph Jensen, Plant Manager

Gordon P. Arent, Manager, Regulatory Affairs

Jonathan Rogoff, Esquire General Counsel

Mano K. Nazar, Senior Vice President

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

D. Markwardt, Manitowac County

Board Chairman

N. Crowley, Director, Manitowac

Emergency Management

G. Novickis, Chairman, Kewaunee

County Board

The Honorable Darin A. Jeanquart

G. Buckley, Two Rivers City Manager

L. Hucek, Director, Kewaunee

Emergency Management

C. Meyer, President, Village of Mishicot

INPO

A. Cayia -5-

ADAMS Distribution:

WDR

DFT

DWS

H. Nieh (HKN), OEDO

Project Director, NRR

Project Mgr., NRR

RidsNrrDipmlipb

JLC1

GEG

HBC

RML2

SRI Point Beach

DRPIII

DRSIII

PLB1

JRK1

Page 1 of 2 Point Beach

08/25/2003 13:19:18 Inspection / Activity Plan

Report 22

09/01/2003 - 09/30/2004

Unit No. of Staff Planned Dates Inspection

Number Inspection Activity Title on Site Start End Type

BR7 - 95003--ENGINEERING, OPS, AND MAINT 5

1, 2 IP 95003 Inspection For Repetitive Degraded Cornerstones, Multiple Degraded Cornerstones, Multiple 09/08/2003 10/15/2003 Supplemental Progra

FY 2004 - POINT BEACH INIT EXAM 10/2003 3

1 W90082 OL - INITIAL EXAM - POINT BEACH - SEP/OCT 2003 09/29/2003 10/03/2003 Not Applicable

71111.08 - ISI AND TI-150 FOR UNIT 2 1

2 IP 2515/150 Reactor Pressure Vessel Head and Vessel Head Penetration Nozzles (NRC Bulletin 2002-0 10/06/2003 10/25/2003 Safety Issues

2 IP 7111108P Inservice Inspection Activities - PWR 10/06/2003 10/25/2003 Baseline Inspections

7112102 - RP ALARA INSPECTION (OUTAGE) 1

1, 2 IP 7112101 Access Control to Radiologically Significant Areas 10/20/2003 10/24/2003 Baseline Inspections

1, 2 IP 7112102 ALARA Planning and Controls 10/20/2003 10/24/2003 Baseline Inspections

71114 - BASELINE EP INSPECTION 1

1, 2 IP 7111402 Alert and Notification System Testing 10/27/2003 10/31/2003 Baseline Inspections

1, 2 IP 7111403 Emergency Response Organization Augmentation Testing 10/27/2003 10/31/2003 Baseline Inspections

1, 2 IP 7111405 Correction of Emergency Preparedness Weaknesses and Deficiencies 10/27/2003 10/31/2003 Baseline Inspections

1, 2 IP 71151 Performance Indicator Verification 10/27/2003 10/31/2003 Baseline Inspections

7112202 - RP RAD MAT'L TRANSPORTATION INSPECTION 1

1, 2 IP 7112202 Radioactive Material Processing and Transportation 12/15/2003 12/19/2003 Baseline Inspections

MOD50.59 - MODIFICATIONS & 50.59 3

1, 2 IP 7111102 Evaluation of Changes, Tests, or Experiments 12/15/2003 12/19/2003 Baseline Inspections

1, 2 IP 7111117B Permanent Plant Modifications 12/15/2003 12/19/2003 Baseline Inspections

IP 71121 - RP PRE-OUTAGE ALARA PLANNING AND CONTROL 1

1, 2 IP 7112101 Access Control to Radiologically Significant Areas 01/26/2004 01/30/2004 Baseline Inspections

1, 2 IP 7112102 ALARA Planning and Controls 01/26/2004 01/30/2004 Baseline Inspections

1, 2 IP 71151 Performance Indicator Verification 01/26/2004 01/30/2004 Baseline Inspections

IP 71121 - RP OUTAGE ALARA & ACCESS CONTROL INSP 1

1, 2 IP 7112101 Access Control to Radiologically Significant Areas 04/12/2004 04/16/2004 Baseline Inspections

1, 2 IP 7112102 ALARA Planning and Controls 04/12/2004 04/16/2004 Baseline Inspections

ISI/TI 1 - INSERVICE INSPECTION & TI-150 UNIT 1 2

1, 2 IP 2515/150 Reactor Pressure Vessel Head and Vessel Head Penetration Nozzles (NRC Bulletin 2002-0 05/03/2004 05/14/2004 Safety Issues

1, 2 IP 7111108P Inservice Inspection Activities - PWR 05/03/2004 05/14/2004 Baseline Inspections

SSDI - SAFETY SYSTEM DESIGN INSPECTION 5

1, 2 IP 7111121 Safety System Design and Performance Capability 06/28/2004 07/16/2004 Baseline Inspections

IP 71122 - RP LIQ/GAS EFFLUENTS INSPECTION 1

1, 2 IP 7112201 Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems 07/26/2004 07/30/2004 Baseline Inspections

1, 2 IP 71151 Performance Indicator Verification 07/26/2004 07/30/2004 Baseline Inspections

This report does not include INPO and OUTAGE activities.

This report shows only on-site and announced inspection procedures.

Page 2 of 2 Point Beach

08/25/2003 13:19:18 Inspection / Activity Plan

Report 22

09/01/2003 - 09/30/2004

Unit No. of Staff Planned Dates Inspection

Number Inspection Activity Title on Site Start End Type

HTSNKB - HEAT SINK BIENNIAL (DRS) 1

1, 2 IP 7111107B Heat Sink Performance 09/13/2004 09/17/2004 Baseline Inspections

71114 - BASELINE EP EXERCISE INSP 2

1, 2 IP 7111401 Exercise Evaluation 09/13/2004 09/17/2004 Baseline Inspections

1, 2 IP 71151 Performance Indicator Verification 09/13/2004 09/17/2004 Baseline Inspections

This report does not include INPO and OUTAGE activities.

This report shows only on-site and announced inspection procedures.