ML20195H687

Draft NRC Insp Manual,Inspection Procedure 71150, Plant Status

ML20195H687
Person / Time
Issue date:	04/21/1999
From:	NRC
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ML20195H628	List: ML20195H623 ML20195H631 ML20195H638 ML20195H647 ML20195H662 ML20195H670 ML20195H676 ML20195H687 ML20195H707 ML20195H735
References
71150, NUDOCS 9906170113
Download: ML20195H687 (6)

Text

i PSTATUS.WPD NRC INSPECTION MANUAL PIPB INSPECTION PROCEDURE 71150 PLANT STATUS CORNERSTONES: ALL INSPECTION BASES: The knowledge of plant activities is important in the risk informed inspection process for determining how to select and implement the other baseline inspection procedures. The inspection will focus on understanding of emergent plant issues, potential adverse trends, current equipment problems, and ongoing activities, including their impact on plant risk.

LEVEL OF EFFORT: Observation of daily activities necessary to ensure an appropriate level of understanding include routine control room and plant walkdowns of all safety-significant plant areas including areas that contain equipment included within the scope of the maintenance rule, areas with significant radiological hazards, and areas with important physical security equipment. In addition, this effort would include attendance at licensee shif t turnovers and management plant status meetings.

-01 INSPECTION OBJECTIVE Ensure inspectors are aware of current plant and equipment problems and have an understanding of the proposed or ongoing site activities from a risk perspective. Inspectors should utilize plant specific risk information as input to what systems are most risk significant given present plant configuration.

-02 INSPECTION REQUIREMENTS:

02.01 Control Room Walkdown

a. Several times per week observe the status of the safety or risk important systems by observing the indicated parameters and equipment configuration indications on the control boards. Determine if any system components are in unexpected issue Date: #21/99 DRAFT ~

_ DRAFT 9906170113 990520 l PDR REVGP ERGNUMRC

[ PDR

configurations, or if-paramaters are at unexpscted values based on the operational mode of the plant. In addition, note whether any significant plant parameter trends exist and whether the licensee' is aware of the trends. Identify '

whether the plant is in any technical specification (TS) limiting ' conditions for operation (LCOs), whether the TS action statements are being met, and that TS requirements and license conditions are being met. Review in the control room, or other appropriate locations, visible portions of

-radiation monitor indications that could provide indication j of.an apparent uncontrolled release. i

b. Several times-per week review ~ control room logs, . equipment out-of-service or. clearance logs, chemistry logs, standing orders, and night orders to understand the activities and problems that occurred since the previous review. Determine whether the logs appropriately reflect the plant status observed during the control board walkdown or that TS requirements are not being met.

c. Weekly review temporary modification logs, operator workaround lists, and temporary shielding logs to determine whether safety / risk important items have been added since the previous review.

02.02 Status Meetinas Several times per week select a complement of licensee meetings

.. that provide an overall status of the plant and of the licensee's activities that are planned or in progress for the safety and risk significant equipment. These meetings could include the licensee's plan of the day meeting, shift turnover meeting, emergent work meeting, equipment prioritization meeting, and corrective action document review meeting, as appropriate.

02.03- Plant Tours Weekly tour accessible areas of the plant containing safety and risk significant t.;tructures, systems, and components (SSCs) within the scope of the maintenance rule, areas that contain significant radiological hazards, and areas with important physical security equipment.

Observe and assess:  ;

a. whether any plant activities are taking place that may affect the operability of the required SSCs and/or increase plant risk. Verify that degraded components have been identified by the-licensee in the corrective action program.

b. The 'overall status of plant SSCs, including general material condition that could affect the SSC's function, and the installation of unauthorized modifications.

c. Plant' areas for fire he.zards that could increase risk, and for overall status of fire protection equipment.

.d. the status of emergency response facilities.[ Monthly) 2

i

o. The status of physical security equipment. Where problems l exist, are the problems being appropriately compensated, and i events properly logged.

f. That doors to locked high radiation areas are locked and that radiation postings are appropriate.

g. Any leakage involving radioactive liquids or ga.ses not bounded by plant collection systems.

02.04 Problem Identification 1

a. Periodically observe licensee management's review of plant  :

deficiencies. ),

b. Selectively review the licensee's deficiency or non-conformance reports to assess whether those problems identified in the logs, from status meetings, and from previous control room walkdowns and plant tours, that ]

increase risk were entered into the corrective action program, are properly characterized, and appropriately classified. Followup will be performed under other inspection procedures.

-03 INSPECTION GUIDANCE:

Issues found during the performance of the plant status reviews should be directly assigned to the applicable cornerstone.

The attached table shows those minimal effort activities included '

in plant status that directly relate to other inspectable area activities. The activities are included in Plant Status because they can be easily accomplished as part of getting plant status without expending more than minimal direct inspection time.

03.01 Control Room Walkdown

a. The inspector should pay particular attention to equipment out of position or indications of degraded plant conditions.

In those cases, the inspector should assess the risk significance in relation to the Reactor Safety cornerstones.

b. The purpose of the log review is to ensure the inspector has an adequate perspective on the current risk importance of the near term problems. Multiple cornerstones could apply to this aspect since radiological safety, emergency preparedness, and physical security aspects could appear in the logs.

03.02 Status Meetinas The purpose of attending the status meetings is to gather information about overall site activities in order to assess what risk important activities will or are being conducted so that inspection resources can be appropriately focused on those with the highest risk. Any combination of meetings that provide the overall perspective to the inspector will accomplish the objective. All cornerstones apply to this activity.

Issue Date: 4/21/99 DRAFT DRAFT

03.03 Plant Tours The purpose of the tours is to provide an independent perspective of ongoing plant problems that increase risk. In performing the tours the inspector should keep in mind the integrated affect of plant' problems on risk. In some cases multiple. problems'at a particular location can have a greater risk than the problems can ,

have individually. All cornerstones apply to this activity. '

03.04 Problem Identification i

The inspector should focus on- whether the licensee uses the corrective action program to identify. problems. In addition, for significant problems the inspector should pay particular attention

• to whether the' licelsee properly classifies the problem in the corrective action program. Proper classification of the condition will- generally cause the appropriate devotion of resources to 1 identify the root cause and correct the problem. All cornerstones apply to this activity. This activity is directly tied to the Identification and Resolution of Problems Inspectable Area. If problems 'are appropriately described and classified in the corrective action program the effectiveness of the inspections conducted under other inspegtion procedures will have a greater probability of focusir,1g on risk significant issues.

-04 RESOURCE ESTIMATE This inspection procedure is estimated to take 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per week l

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l ATTACHMENT 1 MINIMAL EFFORT INSPECTIONS CONDUCTED DURING PLANT STATUS I

ACTIVITY INSPECTABLE AREAS, Control board walkdown Equipment Alignment )

l Transient combustibles and Fire Protection {

ignition sources ]

1 Problem identification review Identification & resolution of problems Locked high rad doors PI verification unauthorized modifications Plant modifications radioactive liquid or gas PI verification leakage not bounded by plant collection systems 1

l Issue Date: 4/21/99 DRAFT DRAFT

ATTACHMENT 2 PLANT STATUS LOGlO CHART l

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