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#REDIRECT [[IR 05000244/2010001]]
{{Adams
| number = ML100620833
| issue date = 03/03/2010
| title = Annual Assessment Letter (Report 05000244-10-001)
| author name = Collins S
| author affiliation = NRC/RGN-I/DRP/PB1
| addressee name = Carlin J
| addressee affiliation = R. E. Ginna Nuclear Power Plant, LLC
| docket = 05000244
| license number = DPR-018
| contact person =
| case reference number = IR-10-001
| package number = ML100541651
| document type = Inspection Plan, Letter
| page count = 5
}}
See also: [[see also::IR 05000244/2010001]]
 
=Text=
{{#Wiki_filter:UNITED STATES 
NUCLEAR REGULATORY COMMISSION 
REGION I 
475 ALLENDALE ROAD 
KING OF PRUSSIA, PENNSYLVANIA 19406-1415 
March 3, 2010
Mr. John T. Carlin
Vice President R. E. Ginna Nuclear Power Plant
R. E. Ginna Nuclear Power Plant, LLC 
1503 Lake Road 
Ontario, NY 14519 
SUBJECT: 
ANNUAL ASSESSMENT LEDER ~ R. E. GINNA NUCLEAR POWER PLANT 
(REPORT 05000244/2010001) 
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 ~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 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 http://www.nrc.gov/reading
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 (R1DR~oII 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
ML100620833
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
SCollins/SJC 
03/0112010
03/01/10
03/01/10
03/01/10
OFFICIAL RECORD COPY
I
 
0211912010
Page 1 012
Report2Z
1
1
1
1
1
10:14:25
Planned Dates 
Start
End 
01/1112010
01/1512010
01/1112010
01f15/2010
0210812010
0211212010
0210812010
0211212010
0210812010
02/1212010
02/08/2010
0211212010
02108/2010
02112/2010
02108/2010
0211212010
0210812010
0211212010
05/2412010
0512812010
06121/2010
0710212010
0312212010
03/26/2010
05ii7i20iQ
OS/2812010
05/1712010
0512812010
05124/2010
05/2812010
0610712010
06111/2010
0612112010
06125/2010
06121/2010
06125/2010
1110812010
11/12/2010
0912712010
1010112010
0912712010
10/0112010
09/27/2010
10/0112010
10/1812010
10/22/2010
11/0112010
11/1212010
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.
 
Page 2 012
02/1912010
10:14:25
Report 22
Planned Dates
Start
End
0110312011
01/0712011
03128/2011
0410112011
1
03/2812011
04/01/2011
1
03/2812011
04f01/2011
0312812011
0410112011
0312812011
0410112011
04/04/2011
0410812011
05/0912011
05/2012011
05/09/2011
05/2712011
05/0912011
05127/2011
05/0912011
05/2712011
05/0912011
05127/2011
05/09/2011
05i27i20ii
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.
}}

Latest revision as of 06:19, 14 January 2025

Annual Assessment Letter (Report 05000244-10-001)
ML100620833
Person / Time
Site: Ginna Constellation icon.png
Issue date: 03/03/2010
From: Collins S
Reactor Projects Branch 1
To: John Carlin
Ginna
Shared Package
ML100541651 List:
References
IR-10-001
Download: ML100620833 (5)


See also: IR 05000244/2010001

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION I

475 ALLENDALE ROAD

KING OF PRUSSIA, PENNSYLVANIA 19406-1415

March 3, 2010

Mr. John T. Carlin

Vice President R. E. Ginna Nuclear Power Plant

R. E. Ginna Nuclear Power Plant, LLC

1503 Lake Road

Ontario, NY 14519

SUBJECT:

ANNUAL ASSESSMENT LEDER ~ R. E. GINNA NUCLEAR POWER PLANT

(REPORT 05000244/2010001)

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 ~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 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 http://www.nrc.gov/reading

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 (R1DR~oII 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

ML100620833

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

I

NPerry/NP

GDentellGTD

DLew/DCL

SCollins/SJC

03/0112010

03/01/10

03/01/10

03/01/10

OFFICIAL RECORD COPY

I

0211912010

Page 1 012

Report2Z

1

1

1

1

1

10:14:25

Planned Dates

Start

End

01/1112010

01/1512010

01/1112010

01f15/2010

0210812010

0211212010

0210812010

0211212010

0210812010

02/1212010

02/08/2010

0211212010

02108/2010

02112/2010

02108/2010

0211212010

0210812010

0211212010

05/2412010

0512812010

06121/2010

0710212010

0312212010

03/26/2010

05ii7i20iQ

OS/2812010

05/1712010

0512812010

05124/2010

05/2812010

0610712010

06111/2010

0612112010

06125/2010

06121/2010

06125/2010

1110812010

11/12/2010

0912712010

1010112010

0912712010

10/0112010

09/27/2010

10/0112010

10/1812010

10/22/2010

11/0112010

11/1212010

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.

Page 2 012

02/1912010

10:14:25

Report 22

Planned Dates

Start

End

0110312011

01/0712011

03128/2011

0410112011

1

03/2812011

04/01/2011

1

03/2812011

04f01/2011

0312812011

0410112011

0312812011

0410112011

04/04/2011

0410812011

05/0912011

05/2012011

05/09/2011

05/2712011

05/0912011

05127/2011

05/0912011

05/2712011

05/0912011

05127/2011

05/09/2011

05i27i20ii

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

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.