ML100620833

Annual Assessment Letter (Report 05000244-10-001)

ML100620833
Person / Time
Site:	Ginna
Issue date:	03/03/2010
From:	Collins S J Reactor Projects Branch 1
To:	Carlin J T Ginna
Shared Package
ML100541651	List: ML100620833 ML100690412 ML101031395
References
IR-10-001
Download: ML100620833 (5)

See also: IR 05000244/2010001

Text

UNITED NUCLEAR REGULATORY

REGION 475 ALLENDALE KING OF PRUSSIA, PENNSYLVANIA

March 3, 2010 Mr. John T. Carlin Vice President

R. E. Ginna Nuclear Power Plant R. E. Ginna Nuclear Power Plant, 1503 Lake Ontario, NY

ANNUAL ASSESSMENT

LEDER R. E. GINNA NUCLEAR POWER (REPORT

Dear Mr. Carlin: On February 12, 2010, the NRC staff completed

its performance

review of R. E. Ginna Nuclear Power Plant (Ginna). Our technical

staff reviewed performance

indicators (Pis) for the most recent quarter and inspection

results for the period from January 1 through December 31, 2009. 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.

This performance review

and enclosed inspection

plan do not include security information.

A separate letter designated

and marked as "Official

Use Only-Security

Information" will include the security cornerstone

performance

review and resultant

inspection

plan. Overall, Ginna operated in a manner that preserved

public health and safety and met all cornerstone

objectives

with moderate degradation

in safety performance.

Plant performance

for the most recent quarter was within the Degraded Cornerstone

column of the NRC's Action Matrix. based on two findings having low to moderatei

safety Significance (White) and one White PI in the Mitigating

Systems Cornerstone.

The first White finding, originating

in the first quarter 2009, was related to Ginna's inadequate

implementation

of a preventive

maintenance (PM) program for, and the subsequent

failure of, the turbine-driven

auxiliary

feedwater (TDAFW) pump governor.

The second White finding. originating

in the fourth quarter 2009, was related to inadequate

corrective

actions which led to binding of the governor control valve and failure of the same TDAFW pump. Additionally, the assigned White PI resulted from exceeding

the White significance

threshold

for the Mitigating

Systems Performance

Index (MSPI), Heat Removal Systems PI, in the third quarter 2009, due to the reliability

and unavailability

issues associated

with the TDAFW pump. In addition to reactor oversight

process (ROP) baseline inspection

at your facility, based on our current assessment

of performance

for Ginna, we plan to conduct a supplemental

inspection

using Inspection

Procedure

95002, "Inspection

for One Degraded Cornerstone

or Any Three White Inputs in a Strategic

Performance

Area." The NRC has previously

conducted

inspections (Ml093160122, ML093160200

and ML091250233)1

to ensure that deficiencies

associated

with the TDAFW pump have been corrected.

However, this inspection

will be conducted, when your staff notifies us of your readiness, to provide assurance

that the root and contributing

causes for the risk significant

performance

issues are understood, to independentty

assess the extent of I DeSignation

in parenthesis

refers to an ADAMS accession

number. Documents

referenced

in this letter are publicly available

using the accession

number in ADAMS

J. Carlin 2 condition and extent

of cause, to Independently

detennine

if safety culture components

contributed

to the performance

issues, and to provide assurance

that the corrective

actions are sufficient

to prevent recurrence.

The enclosed inspection

plan details the inspections, less those related to security, scheduled

through June 30, 2011. In addition to the previously

noted 95002 supplemental

inspection

and the baseline inspections, we plan on conducting

independent

spent fuel storage installation (ISFSI) inspections.

The inspection

plan is provided to allow for the resolution

of any scheduling

conflicts

and personnel

availability

issues well in advance of inspector

arrival onsite. Routine resident inspections

are not listed due to their ongoing and continuous

nature. The inspections

in the last nine months of the inspection

plan are tentlative

and may be revised at the mid-cycle

review. In accordance

with 10 CFR 2.390 of the NRC's

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/readingrm/adams.html (the Public Electronic

Reading Room). If circumstances

arise which cause us to change this inspection

plan, we will contact you to discuss the change as soon as possible.

Please contact Glenn Dentel of my staff at 610-337-5233

with any questions

you may have regarding

this letter or the inspection

plan. Sincerely, Regional Administrator, Region I Docket No. 50-244 License No. DPR-18 Enclosure:

Ginna Inspection

I Activity Plan cc w/encl: Distribution

via ListServ

OFFICE NAME DATE J. Carlin 2 condition

and extent of cause, to independently

determine

if safety culture components

contributed

to the performance

issues, and to provide assurance

that the corrective

actions are sufficient

to prevent recurrence.

The enclosed inspection

plan details the inspections, less those related to security, scheduled

through June 30, 2011. In addition to the previously

noted 95002 supplemental

inspection

and the baseline inspections, we plan on conducting

independent

spent fuel storage installation (ISFSI) inspections.

The inspection

plan is provided to allow for the resolution

of any scheduling

conflicts

and personnel

availability

issues well in advance of inspector

arrival onsite. Routine resident inspections

are not listed due to their ongoing and continuous

nature. The inspections

in the last nine months of the inspection

plan are tentative

and may be revised at the mid-cycle

review. In accordance

with 10 CFR 2.390 of the NRC's "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

rmfadams.html (the Public Electronic

Reading Room). If circumstances

arise which cause us to change this inspection

plan, we will contact you to discuss the change as soon as possible.

Please contact Glenn Dentel of my staff at 610-337-5233

with any questions

you may have regarding

this letter or the inspection

plan. Sincerely, IRA! Samuel J. Collins Regional Administrator, Region I Docket No. 50-244 License No. DPR-18 Distribution

w/encl: (via E-mail) S. Collins, RA (R1AMAIL RESOllRCE)

M. Dapas. IlRA(R1MA1LRt!SOURCEI

D. Lew, ORP (R1IlR_RESOURCE)

J. Clifford, DRP (R1DRPMAIL

RESOllRCIE)

D. Roberts, DRS

R"o_1 P. Wilson, DRS (R1PRS ..... 1R**.,.)

L. Trocine, RI OEDO G. Dantel. DRP N.Peny,DRP

J. Hawkins, DRP S. Sloan, ORP K. Kolaczyk, DRP. SRI L. Casey, DRP, RI M. Rose, DRP. OA RidsNrrPMREGinna

Res()urce

RldsNrrOorlLpl1-1

Resource SUNSI Review Complete:

_N:.:,:P"'--

___(Reviewer's

Initials)

DOCUMENT NAME: S:\ROP*10

EOC Revlew\Branch

1\Ginna AA Letter 2.doc RQPreportsResource@nrc.gov

ORS Branch Chiefs (6) L. Scholl, DRS D.Silk, DRS J. Trapp, DRS D. Serenci, PAO N. Sheehan, PAO R. Barkley, ORA ML 100620833

After declaring

this document "An Official Agency Record" it will be released to the Public. To receive a copy of this document, indicate In the box: "C*;:: Copy without attachment/enclosure "En", Copy with attachment/enclosure

uN" ... No copy RI/DRP I RIIDRP I RIIDRP I RI/ORA NPerry/NP

GDentellGTD

DLew/DCL

03/0112010

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Ginna Inspection

/ Activity Plan 01/01/2010

-0613012011

Titi" 71124 -RADIATION

SAFETY 1 lP 71124.01 Radiological

Hazard Assessment

and Exposure Controls IP 71124.02 Occupational

ALARA Planning and Controls EP PROG -EP PROGRAM INSPECTION

IP 7111402 Radiological

Environmental

Monitoring

Program IP 7111403 Emergency

Response Organization

Augmentation

Testing IP 7111404 Emergency

Action Level and Emergency

Plan Changes lP 7111405 Correction

of Emergency

Preparedness

Weaknesses

and Deficiencies

IP 71151-EP01

DrilllExercise

Performance

IP 71151-EP02

ERO Drill Participation

IP 71151-EP03

Alert & Notification

System 6f21EXAM -OPERATOR LICENSING

INITIAL EXAMS 5 U01766 FY10 -GINNA INITIAL OPERATOR LICENSING

EXAM U01766 FY10 -GINNA INITIAL OPERATOR LICENSING

EXAM 71124.08 * RAD SOLID WASTE PROCESS AND RAD MATL HAN 1 lP 71124.08 Radioactive

Solid Waste Processing

and Radioactive

Material Handling, Storage. and Transportation

ISFSI -ISFSI DRY RUN AND INITIAL LOADING IP 80854 Preoperational

Testing Of An ISFSI IP 80855 Operation

Of An ISFSI 71152B *PI&R 4 IP 711528 Identffication

and Resolution

of Problems IP 711528 Identification

and Resolution

of Problems 2515/173 -INDUSTRY

GROUND WATER INITIATIVE

IP 2515/173 Review of the Implementation

of the Industry Ground Water Protection

Voluntary

Inttlative

71124.07 .REMP 1 IP 71124.07 Public Radiation

Safety 711111 B -REQUAL INSP WI P/F RESULTS 3 IP 71111118 Licensed Operator Requallficatlon

Program 71124 -RAD SAFElY -RAe HAZZARD ASSESSIALARA

IP 71124.01 Radiological

Hazard Assessment

and Exposure Controls lP 71124.02 Occupational

ALARA Planning and Controls IP 71151 Performance

Indicator

Verification

CDBI * COMPONENT

DESIGN BASES INSPECTION

6 IP 7111121 Component

Design Bases Inspection

IP 7111121 Component

Design Bases Inspection

his report does not inClude INPO andOlJTAGE

activities.

This report shows only on-site and announced

inspection

procedures.

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71124.05 IP 71124.05 71124.01 IP 71124.01 IP 71124.02 lP 71124.03 IP 71124.04 lP 71124.05 TI-177 IP 2515/177 7111108P IP 7111108P 71124.01 IP 71124.01 IP 71124.02 IP 71124.03 IP 71124.04 iP 71124.05 Ginna Inspection

/ Activity Plan 01/0112010

-0613012011

Title -RAD INSTRUMENTATION

Radiation

Monitoring

Instrumentation

-RAe HAZZARD ASSESS, ALARA, AIR, DOSE 1 Radiological

Hazard Assessment

and Exposure Controls Occupational

ALARA Planning and Controls In*Plant Airborne Radioactivity

Control and Mitigatlon

Occupational

Oose Assessment

Radiation

Monitoring

InstrumentatiQn

• MANAGING GAS ACCUMULATION

IN ECCS 2 Managing Gas Accumulatlon

In Emergency

Core Cooling, Decay Heat Removal 8. Containment

Spray System *INSERVICE

INSPECTION

1 Inservice

Inspection

Activities

-PWR -RAD HAZARD ASSESS, ALARA, AIR, DOSE 1 Radiological

Hazard Assessment

and Exposure Controls Occupational

ALARA Planning and Controls In-Plant Alrborne Radioactivity

Control and MitigatJon

OccupatJonal

Dose Assessment

Radiation

ivionitoring

Instrumentation

is report does not include INPO and OUTAGE activities.

This report shows only on-site and announced

inspection

procedures.