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NRC INSPECTION MANUAL PECB

INSPECTION PROCEDURE 90700

FEEDBACK OF OPERATIONAL EXPERIENCE INFORMATION

AT OPERATING POWER REACTORS

PROGRAM APPLICABILITY: 2515

SALP FUNCTIONAL AREA: ENGINEERING (ENG)

90700-01 INSPECTION OBJECTIVE

To determine the effectiveness of licensees' programs to assess and

feed back 

to plant staff operational experience information pertinent to

plant safety 

originating both within and outside the licensees' organizations.

90700-02 INSPECTION REQUIREMENTS

02.01 Program verification. Verify the existence of a licensee

program for 

tracking and accounting operational experience information.

02-02 Procedure Review. Review and determine the effectiveness

of the 

procedures utilized by the licensee to implement the operational

experience 

feedback program. Determine that the licensee's procedures that

implement the 

operational experience program:

a. Identify organizational responsibilities for review and

prioritization of operational experience information, the

feedback of pertinent operational experience information to

operators and other personnel, and the incorporation of such

information into training and retraining personnel.

b. Identify the administrative and technical steps necessary in

translating recommendations by the operational experience

information assessment group into plant actions (e.g.

procedures, lesson plans, or design changes).

c. Identify the recipients of various categories of information

from operational experience information or otherwise provide
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means through which such information can be readily related

to the job functions of the recipients.

d. Provide assurance that affected personnel are aware of and

understand operational experience information of sufficient

importance that should not wait for a plant procedure change

or emphasis through routine training and retraining programs.
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e. Provide assurance that conflicting or contradictory

information is not conveyed to operators and other personnel

until resolution is reached.

f. Provide for periodic internal audits to assure that the

feedback program functions effectively at all levels.

02.03 Program Assessment. Determine the overall effectiveness

of the licensee's operational experience feedback process by

selecting and following up operational experience reports received,

reviewed, and dispositioned by the licensee.

a. Verify the receipt, review, and disposition by the licensee

of six known operational experience information reports.

b. Select at least six diverse operational experience

information reports pertinent to the facility and received by

the licensee. At least one of the six reports selected shall

be from a 10 CFR Part 21 notification.

1. Determine the completeness and timeliness of the

licensee's review and assessment of the selected

operational experience information reports.

2. Determine the appropriateness, quality, and timeliness of

corrective actions -- including training -- taken or

planned by the licensee, if corrective actions (including

training) were necessary or appropriate.

3. Verify the completion of corrective actions by reviewing

procedures, lesson plans, and design changes.

4. To assess the effectiveness of the licensee's corrective

actions compare the licensee's current deficiency/problem

reports (both performance and hardware issues) to the

operational experience information reports selected above

to identify whether similar problems continue to occur.

90700-03 INSPECTION GUIDANCE

General Guidance

NUREG-0737, Item I.C.5, required licensees to develop procedures to

feedback operational experience information to plant staff. The NRC

staff, in Generic Letter 82-04, indicated that participation by

licensees in the Significant Event Evaluation and Information

Network (SEE-IN) program administered by the Institute of Nuclear

Power Operations (INPO) would enhance a licensee's ability to meet

the intent of NUREG-0737, Item I.C.5, but would not relieve a

licensee from taking those actions specific to the licensee's

nuclear unit which result from an evaluation of operational

experience information. INPO periodically evaluates licensees'

participation in the SEE-IN program. Inspectors should be cognizant

of INPO's activities in this area.

For review of INPO documents, the inspector should not reference
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specific documents nor discuss INPO findings, recommendations, and

corrective actions in the inspection report. The purpose of this

review is to verify the adequacy of the licensee's processes for

implementing its program for operational feedback.

The use of INPO information is discussed in a revised Memorandum of

Agreement between INPO and the NRC dated September 17, 1993.

Additional guidance on the use of INPO information can also be

found in Inspection Procedure 71707, "Operational Safety

Verification."

For the purposes of this inspection procedure, operational

experience information reports are considered to be:

! NRC bulletins, generic letters, and information notices.

! Reports generated by industry-affiliated organizations (Such

as significant event reports [SER's], significant event

notifications [SEN's], and significant operating experience

reports [SOER'S] generated as a result of the INPO SEE-IN

process).

! 10 CFR Part 21 and related reports (such as germane to safety

reports issued by General Electric Company) generated by

vendors and other licensees.

! Other vendor related reports (such as service information

letters [SIL's] and rapid information communication service

information letters [RICSIL'S] issued by General Electric

Company).

! Reports resulting from employee concern programs or from

concerns brought by external persons or organizations.

! Reports resulting from internally identified problems.

! Other reports, as appropriate.

Headquarters should be notified if information is developed that

may indicate the existence of a generic safety issue that may not

be known to headquarters. Notifications can be made through

Inspection Manual Chapter (IMC) 0230, "Morning Report," or (IMC)

0970, "Potentially Generic Items Identified by Regional Offices."

When providing information to headquarters, be sensitive to

pertinent information that may not be readily available in

headquarters.

NRR may also request, at times, that specific operational

experience information reports (such as bulletins and generic

letters) be inspected at the site. In such cases, guidance to

perform such inspections will be transmitted through a temporary

instruction (TI).

Specific Guidance
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No specific guidance provided.

90700-04 INSPECTION RESOURCES

Direct inspection resources necessary to complete this inspection

procedure are estimated to be12 hours per reactor facility.

90700-05 REFERENCES

NUREG-0737, "Procedures for Feedback of Operating Experience to

Plant Staff," Item I.C.5.

Generic Letter 82-04, "Use of SEE-IN Program."

END