ML20235E196

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Forwards,For Review,Draft Rev 0 to Master Insp Plan for Facility.Plan Based on Insp Recommendations Provided by Each Responsible Technical Section.Corrections Requested by 870708
ML20235E196
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 07/01/1987
From: Landis K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Brownlee V, Gibson A, Reyes L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8707100453
Download: ML20235E196 (17)


Text

- - _ _ _ _ - _ _ _ _ _ _

h'/

F

'JUL01 Sid l

NOTE FOR:

Luis A. Reyes, Director, Divisions of Reactor Projects l

Philip J. Stohr, Director, Division of Radiation Safety and Safeguards Albert F. Gibson, Director, Division of Reactor Safety Virgil L. Brownlee, Chief, Reactor Projects Branch 2 DivisionofReactorProjects FROM:

Kerry D. Landis, Chief, Technical Support Staff DivisionofReactorProjects

SUBJECT:

DRAFT REVISION 0 0F THE MASTER INSPECTION PLAN FOR V0GTLE UNIT 1 i

Enclosed is Draft Revision 0 of the Master Inspection Plan for Vogtle Unit 1.

This inspection plan was developed based on the inspection recommendations provided to me by each responsible technical section.

Please note that for those modules which the responsible technical section has l

recommended to not perform, we have annotated this appropriately by a line drawn through them.

Also, those recommended changes from the MC 2515 inspec-tion frequency are annotated by a pen-and-ink change.

Please review the drafL and report any corrections or changes to John Zeiler at extension 0345 by Wednesday, July 8, 1987.

Original Signed by Kerry Landis Kerry D. Landis

Enclosure:

Draft Master Inspection Plan, Revision 0 for Vogtle Unit 1, with Attachment 1 cc w/ enc 1:

A. Herdt, DRS T. Conlon, DRS J. Blake, DRS C. Juiian, DRS 1

J. Munro, DRS G. Belisle, DRS M. Shymlock, DRS W. Rankin, DRSS W. Cline DR l

E.McAlpine,SS l

DRSS G. Troup, DRSS J. Potter, DRSS D. Collins, DRSS J. Kahle, DRSS (cc w/ encl cont'd - see page 2) i 8707100453 870701 ADDCK 0500 4

gDR s(

L:ot

ryjt 01I' Multiple Addressees 2

(cc w/ enc 1 cont'd)

T. Decker, DRSS 1

C. Hosey, DRSS D. McGuire, DRSS M. Sinkule, DRP g

SR$ o tle 4

RI RIIj JZ er:cdg KLa 06/ D/87 06/$t/87 3

___________A

n DRAFT MASTER INSPECTION PLAN REVISION 0 FACILITY:

V0GTLE UNIT 1 Approved By:

Division Director DRAFT

MASTER INSPECTION PLAN REVISION 0 Facility: Vogtle Unit 1 Latest SALP Period: 07/01/85 - 09/30/86 MC 2515 RECOMMENDED PROCEDURE INSPECTION NUMBER TITLE FREQUENCY RESPONSIBILITY Plant Operations - Latest SALP Rating: See Attachment 1 MINIMUM 71707 Operational Safety Verification D/WK/BWK RI 71710 ESF System Walkdown BM RI 92709 Licensee Plans for Coping with W

RI Strikes (Every 3 years and prior to impending strikes) 92710 Licensee's Initial Implementation of W

RI Strike Plans (At plant turnover to non-striking personnel) 92711 Continued Implementation of Strike W

RI Plans During Extended Strike (Weekly for the duration of the strike) 92712 Resumption of Normal Operation After W

RI Strike (During plant turnover to returning plant personnel) i 93702 Onsite Followup of Events at Operating W

RI Power Reactors BASIC 71714 Cold Weather Preparations W

RI i

SUPPLEMENTAL j

12700 Plant Procedure; W

RI 71715 S' g tched Centr:1 "ccm and "hnt W

RI

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V V

b Ib wb I V

F wb y

b yy

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~

UNAFI i'

Radiological Controls - Latest SALP R.ating:

See Attachment 1 MINIMUM 83722 Radiation Protection, Plant Chemistry, A

FRP and Radwaste: Organization and Management Controls 83723 Training and Qualifications: General, A

FRP Employee Training, Radiation Safety, Plant Chemistry, Radwaste, and Transportation 83724 External Occupational Exposure A

FRP Control and Personal Dosimetry l

83725 Internal Exposure Control and A

FRP l

Assessment l

83726 Control of Radioactive Materials and A

FRP Contamination Surveys, and Monitoring 83728 Maintaining Occupational Exposures A

FRP ALARA 84722 Solid Wastes A

FRP 84723 Liquids and Liquid Wastes A

REC 84724 Gaseous Waste System A

REC 84725 Quality Assurance and Confirmatory A

REC Measurements for In-Plant Radio-chemical Analysis 8ASIC 71709 Radiological Protection Procedures M/Q/

RI for the Resident Inspector 11 79701 LWR Water Chemistry Control and A

REC Chemical Analysis 80721 Radiological Environmental 2 yr REC Monitoring 83722 Radiation Protection, Plant Chemistry, A

FRP and Radwaste: Organization and Management Controls 83723 Training and Qualifications: General A

FRP Employee Training, Radiation Safety, Plant Chemistry, Radwaste, and Transportation:

)

I

_o

DRAFI 83724 External Occupational. Exposure A

FRP Control and Personal Dosimetry 83725 Internal Exposure Control and A

FRP Assessment 83726 Control of Radioactive Materials and A

FRP Contamination Surveys, and Monitoring 83727 Facilities and Equipment A

FRP 83728 Maintaining Occupational Exposures A

FRP ALARA 83729 Occupational Exposure During W

FRP Extended Outages 84722 Solid Wastes A

FRP 84723 Liquids and Liquid Wastes A

REC 84724 Gaseous Waste System A

REC 84725 Quality Assurance and Confirmatory A

REC Measurements for In-Plant Radio-chemical Analysis 86721 Transportation A

FRP SUPPLEMENTAL

_b'U,,,S!!..,.5...$'b,,.!.!.U 0 "'

w~,

-- 7C502 Plant Sy; tem: ^'fecting Plant W;ter

'd I,CC Chai;try 0C521

!! diclogical Envircament:1 M nitor ng F

9EC i

83522 Radiation Protection, Plant Chemistry, W

FRP Radwaste, and Environmental:

Organization and Measurement Controls 83523 Radiation Protection, Plant Chemistry, W

FRP Radwaste, Transportation and Environmental:

Training and Qualifications 83524 External Occupational Exposure Control W

FRP and Personal Dosimetry 83525 Internal Exposure Control and W

FRP Assessment 83526 Control of Radioactive Materials W

FRP and Contamination Surveys and Monitoring

~

DRAFT 4

l l

83527 Facilities and Equipme,nt W

FRP 84522 Solid Wastes W

FRP S4523 Liquid: :nd Liquid ';'::te:

t' 9EC 84524 Gaseous Waste System W

REC S4525 Quality S;ur:n

nd Cer: tier REC 1

"easur;n nt; for h p hat Radio-che-ical %21ysis 84850 Radioactive Waste Management -

W FRP l

Inspection of Waste Generator i

Requirements of 10 CFR 20 and 10 CFR 61 86740 Inspection of Transportation W

FRP Activities Maintenance - Latest SALP Rating:

See Attachment 1 MINIMUM 62703 Monthly Maintenance Observation M

RI BASIC 62700 Maintenance Program Implementation 2 yr MPS SUPPLEMENTAL 62702 Maintenance Program W

MPS 62704 Instrumentation Maintenance (Components W

PSS and Systems) Observation of Work, Work Activities, and Review of Quclity Records 62705 Electrical Maintenance (Components W

PSS and Systems) Observation of Work, Work Activities, and Review of Quality Records Surveillance - Latest SALP Rating:

See Attachment 1 MINIMUM

  • 61707 Determination of Reactor Shutdown W

TPS Margin (Performed in Minimum Program following detection of inoperable control rod)

DRAFT

~

~

61726 Monthly Surveillance Observation M

RI

  • Minimum program items indicated by asterisk within each procedure BASIC 61725 Surveillance Testing and Calibration 3 yr QAS Control Program SUPPLEMENTAL E1700 Survcillcnce Precedurc end 9!

--Re c o rd; 61701 Complex Surveillance W

TPS (One major surveillance each refueling outage) 61702 Surveillance of Core Power W'

TPS Distribution Limits 61705 Calibration of Nuclear W

IPS Instrumentation Systems 61706 Core Thermal Power Evaluetion W

TPS 61707 Determination of Reactor Shutdown W

TPS Margin 61708 Isothermal and Moderator Temperature W

TPS Coefficient Determinations 61709 Power Coefficient of Reactivity W

TPS 61710 Control Rod Worth Measurement W

TPS 61728 Independent Measurement of RCS W

TPS 4

Leak Rates for a PWR Performed in Minimum program under IP 72700 for every refueling.

Emergency Preparedness - Latest SALP Rating:

See Attachment 1 MINIMUM 82301 Evaluation of Exercises for Power A

EPS Reactors (Sections 1, 2, and 3) 82701 Operational Status of the Emergency A

EPS Preparedness Program

~

~

DRAFT BASIC 82102 State ef L:te o rcepertien:1 oh:ce u

gp3 Emergency rep;redne:: "regr:p; o

82201 Emergency Detection and A

EPS Classification 82202 Protective Action Decision Making A

EPS 82203 Notifications and Communications A

EPS 4

1 1

82204 Changes to the Emergency Preparedness A

EPS Program 82205 Shift Staffing and Augmentation A

EPS 82206 Knowledge and Performance of A

EPS Duties (Training) 82207 Dose Calculation and Assessment 3 yr EPS 82209 Public Information Program 3 yr EPS 82210 Licensee Audits A

EPS A

82301 Evaluation of Exercises for Power g

EPS Reactors (Sections 4 through 11)

SUPPLEMENTAL 02301 Evaluatica of Exarci3e3 for Power A

EPS

o. ::ter: (Section: ' throu;F 11)

TI 2512/55 Emergency reparedne :

us o

gpg

--Implement: tier ^.pprait:1 "regr:r

'Only perfer :ppropriate cettent.

Fire Protection - Latest SALP Rating:

See Attachment 1 MINIMUM - None.

BASIC 64100 Postfire Safe Shutdown, Emergency W

PSS Lighting and Oil Collection Capability at Operating and Near-Term Operating Reactor Facilities 64150 Triennial Postfire Safe Shutdown 3 yr PSS Capability Reverification 64704 Fire Protection / Prevention Program A

PSS

~

~

DRAFT SUPPLEMENTAL - None.

Security - Latest SALP Rating:

See Attachment 1 MINIMUM

  • 81000 Physical Security A

PSEC Series

  • Minimum program item indicated by asterisk within each procedure.

BASICS 71881 Physical Security Procedures for M/Q RI the Resident Inspector 81018 Security Plan and Implementing A

PSEC Procedures 81020 Management Effectiveness - Security A

PSEC Program 81022 Security Organization A

PSEC 81034 Security Program Audit A

PSEC 81038 Records and Reports A

PSEC 81042 Testing and Maintenance A

PSEC 81046 Locks, Keys, and Combinations A

PSEC 81052 Physical Barriers-Protected Areas A

PSEC 81054 Physical Barrier-Vital Areas, A

PSEC Material Access Areas and Controlled Access Areas 81058 Security System Power Supply A

PSEC 81062 Lighting A

PSEC 81064 Compensatory Measures A

PSEC 81066 Assessment Aids A

PSEC 81070 Access Control-Personnel A

PSEC 81072 Access Control (Power Reactor) -

A PSEC Packages 81074 Access Control-Vehicles A

PSEC 81078 Detection Aids-Protected Areas A

PSEC

DRAFT 81080 Detection Aids-VA, MAA., and CAA A

PSEC 81084 Alarm Stations A

PSEC 81088 Communications A

PSEC S1401 Plan: Pr;;; dure: and 90vi:;;;

W PSEC S1403 Re ipt ;f N ;, Fuel :t R ::ter W

PS C

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a...,

l 31'31

-d Site Physic:1 nretectier of W

PSEC 81501 Personnel Training and Qualifications -

A PSEC General Requirements 81601 Safeguards Contingency Plan A

PSEC Implementation Review A

81810 Physical Protection Safeguards r

PSEC Information 85102 Material Centr:1 and A : enting -

3 yr MC?

90::ter:

2 Regions have the perogative to determine that any inspection program requirements have been fulfilled by Regulatory Effectiveness Reviews (RERs).

Such credit should depend upon the accompanying inspector's judgment, and the conduct of the RER within six months of a scheduled inspection.

2 Upen arrie:1 cf 70; fuel er site.

SUPPLEMENTAL 81000 Physical Security W'

PSEC Series 05102 Material Centr:1 and A : unting -

W MC?

Reacter i

s Increased sample size is required by each IP when performing these inspections under the Supplemental program.

Outages - Latest SALP Rating:

See Attachment 1 MINIMU:4 61720 Containment Local Leak Rate Testing 2 yr TPS 70313 Containment Integrated Leak Rate Test W

TPS Surveillance (performance for each CILRT) l 72700 Startup Testing - Refueling R

TPS 1

~

DRAFT

~

73753 Inservice Inspection. Observation W

MPS

(

of Work and Work Activities (Conduct for PSI, first ISI, thereafter, each outage in which significant ISI, Code i

repair / replacement is performsd)

BASIC 37700 Design, Design Changes and A

RI Modifications

{

61715 Verification of Containment Integrity W

TPS 70307 Containment Integrated Leak Rate Test W

TPS l

Review (performed prior to each CILRT) 70323 Containment Leak Rate Test Results W

TPS Evaluation (performed following each CILRT) 71711 Plant Startup from Refueling R

R1 72701 Modification Testing W

TPS 73051 Inservice Inspection - Review of W

MPS Program (Conduct for PSI, first ISI, thereafter, every other outage for program revisions only and for 10 year program submittal to NRC) 73052 Inservice Inspection - Review of W

MPS i

Procedures (Conduct for PSI, first ISI, thereafter, each outage, keying only procedure revisions) 73755 Inservice Inspection - Data Review W

MPS and Evaluation (Conduct for first ISI thereafter, twice in a 3-outage cycle -

one in-office, one onsite review) 73756 Inservice Testing of Pumps and Valves 3 yr MPS l

SUPPLEMENTAL 37701 Fccility Mcdificctic=

u qi 55050 Nuclear Welding General Inspection W

MPS Procedure 55100 Structural Welding General Inspection W

MPS Procedure 55150 Weld Verification Checklist W

MPS 55700 Celibrctica RI (Performcd ccch refuel %g) 1

)

DRAFT 57050 Nondestructive Examination W

MPS Procedure Visual Examination Procedure Review / Work Observation /

l Record Review 57060

. Nondestructive Examination Procedure W

MPS Liquid Penetrant Examination Procedure Review / Work Observation /

Record Review 57070 Nondestructive Examination Procedure W

MPS Magnetic Particle Examination Procedure Review / Work Observation /

Record Review 57080 Nondestructive Examination Procedure W

MPS Ultrasonic Examination Procedure Review / Work Observation / Record Review 57090 Nondestructive Examination Procedure W

MPS Radiographic Examination Procedure Review / Work Observation / Record Review 60705 Preparation for Refueling W

RI (Prior to first refueling; prior to refueling if SALP 3) 60710 Refueling Activities W

RI (Prior to first refueling; prior to refueling if SALP 3) 70370 Testing of Pipe support and Restraint W

TPS Systems (Performed each refueling)

Licensing Activities - Latest SALP Rating:

See Attachment 1 MINIMUM - None.

BASIC - None.

SUPPLEMENTAL 94702 Participation in NRR/ Licensee W

DRP Meetings (Performed for each meeting attended)

Quality Programs and Administrative Controls Affecting Quality - Latest SALP Rating:

See Attachment 1 MINIMUM 35701 QA Program - Annual Review A

QAS

92703.

IE Bulletin, Confirmatory Action W

DRP Letter, and Generic Letter Followup BASIC 35001 Review of Changes to Quality Assurance W

QAS Program Description 36100 10 CFR Part 21 Inspections W

RI 40700 Onsite Review Committee W3 RI l

40701 Of fsite Review Committee W3 QAS 90712 In-office Review of Written Reports W

ALL of Nonroutine Events at Power Reactor Facilities l

92700 Onsite Followup of Written Reports W

DRP of Nonroutine Events at Power Reactor Facilities 92701 Followup (Note:

The followup of IE W

ALL Information Notices and IE Bulletins sent for information shall be performed annually.)

92702 Followup Items of Noncompliance /

Devi-W ALL ations 92720 Corrective Action 2 yr QAS 3 Performed in Minimum program under IP 35701.

l

. SUPPLEMENTAL 35750 QA Program Measuring and Test Equipment W

QAS (performed each refueling) 36700 Organization and Administration W

RI 37702 Design Change and Modifications Program W

QAS 37703 Test and Experiments Program W7 QAS 38701 Procurement Program W7 QAS 38702 Receipt, Storage, and Handling of W7 QAS Equipment and Materials Program 39701 Records Program W7 QAS j

39702 Document Control Program W7 QAS 40702 Audit Program W7 QAS

DRAFT 40703 Offsite Support Staff W'

QAS

)

40704 Implementation, Audit Program W'

QAS 50005 Spent Fuel Ster:ge R: k:

u or 55051 Leu-Level 9: die::tive W::t Ster:g W

cR" F::i' i tie:

90713 In office Review of Periodic and W

DRP Special Reports (When receive periodic /special report addressed to Region / Headquarters) 90714 Nonroutine Reporting Program W

RI l

7 Performed in Minimum program under IP 35701.

Training and Qualification Effectiveness - Latest SALP Rating:

See Attachment 1 J

MINIMUM 41400 Non licer.3ed Staff Training A'

O." S

?!701 Licen::d Oper:ter Tr: fring OPS

\\

)

'lles in;pcction rc:;uirc Or.t: tutti"; : crc:: Sever:!

ti^"21 2r:2.

l BASIC - None, j

l SUPPLEMENTAL - None.

Others MINIMUM i

30703 Management Meetings-Entrance and W

ALL Exit Interviews (All management meeting unrelated to SALP or item followup as discussed in IPs 92700, 92701, 92702 and 92703)

BASIC 30702 Management Meeting-As Needed W

DRP

SUPPLEMENTAL i

94600 Information Meetings with Local W'

DRP Officials (Performed for each, meeting) 94703 Media Contacts W

RI (Performed for each meeting attended)

' Regional procedures require completion every two years.

l I

_AnACK:UCT 1 ffK ppS

3..

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vocTLE SALP CATEGORY RATINGS

.s 4..>

rend 11/1/83 7/1/85 During 6/30/85 9/30/86 Latest Category Category

$ ALP Rating Rating Period Functional Are s Unit 1 and Unit 2 Construction A.

Soils and Foundations 1

1 B.

Containment, Safety Related 2

1

$tructures and Major Supports C.

Piping Systems and Supports 2

2 D.

Safety Related Components -

1 2

Mechanical E.

Auxiliary Systems 2

2 F.

Electrical Equipment and Cables 2

2 G.

Instrumentation Not Rated 1

H.

Quality Programs and 1

1 Administrative Controls Affecting Quality 1.

Licensing 2

2 J.

Independent Design Review Not Rated 1

K.

Other Licensee Initiatives Not Rated 1

Unit 1 Preoperational Testing A.

Preoperational Testing Not Rated 1

Unit 1 Operations B.

Operational Readiness Not Rated 2

1.

plant Operations 2.

Startup Testing j

g 3.

Surveillance 4

C.

Radiological Controls /

Not Rated 2

Chemistry

~

i 1.

Radiological Controls 2.

Chemistry I

3.

Nuclear Air Cleaning k

t Systems

{

0.

Maintenance Not Rated 2

j E.

Fire Protection Not Raffd 2

F.

Emergency Preparedness Not Rated 1

G.

Physical Security / Material Not Rated 3

Control and Accounta-bility y

H.

Quality Programs and Not. Rated 2

Administrative Controls Affecting Quality r

Operatkaa I.

Training and Quaii(1:stion Not Rated 2

Declining Effectivene<<

Q J