ML19346A076

Environ Qualification of Safety-Related Electrical Equipment,Ie Bulletin 79-01B, Technical Evaluation Rept, Revision 1

ML19346A076
Person / Time
Site:	Farley
Issue date:	12/10/1980
From:	Merriweather N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML19346A074	List: ML19346A073 ML19346A075 ML19346A076 ML19346A077
References
CIVP-A-012, CIVP-A-12, IEB-79-01B, IEB-79-1B, NUDOCS 8106050003
Download: ML19346A076 (15)

Text

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ENVIRONMENTAL QUALIFICATION OF SAFETY-ELATED ELECTRICAL EQUIPMENT IEB 79-01B 4

l TECHNICAL EVALUATION REPOPT DOCKET NO. 50-348 PLANT: Joseph M. Farley Nuclear Plant, Unit 1 DATED: December 10, 1980 REVISION 1 Licensee: Alabama Power Company Type Reactor:

Pressurized Water Reactor i

l Prepared by:

N. Merriweather I

f &..a,M, -

Engineering Support Section No. 1 Reactor Construction and Engineering Support Branch, RII i

i 810 6v5 o oog

d a

TABLE OF CONTENTS PAGE NO.

1.

INTROLUCTILN.........

I 1.1 General I

2.

BACKGROUND AND DISCUSSION.........................................

1 2.1 General....................................................

I 2.2 On-Site Inspection.........................................

2 2.3 Evaluation of Licensee's Report 2

3.

GENERAL INFORMATION...............................................

3 3.1 Identification of Class IE Electrical Systems...............

3 3.2 Service Conditions.........................................

4 3.3 Qualification Documentation................................

4 4.

EQUIPMENT DATE REVIEW.............................................

4 4.1 Qualified Equipment 4

4.2 Equipment With Aging Less Than Plant Life..................

4 4.3 Equipment to be Replaced, Modified, or Relocated - Licensee Identified.................................................

5 4.4 Equipment with Unresolved Qualification Items 5

4.5 Equiprent Not Qualified...

5 4.6 Outstanding Items - Licensee Identified....................

5 4.7 Discussion of On-Site Inspection...........................

6 5.

CONCLUSIONS.......................................................

6 Review Tabulation Sheets Used in Evaluation of Licensee's Report List of Standard Systemsi List of Documents That Support Environmental Qualifica-tion of Licer ee's Equipment Outstanding Items (Licensee Identified) i i

J 1.

INTRODUCTION 1.1 General The NRC Office of Inspection and Enforcement (I/E) issued Bullatin 79-01B, " Environmental Qualification of Class IE Equipment" in January 1980.

This bulletin required the licensee to perform a detailed evaluatioa of the environmental qualification on Class IE electrical equipment required to function under postulated accident conditions and co submit a report on this action.,

t This document is a report on the evaluation of the licensee's response to this bulletin.

2.

BACKGROLWD AND DISCUdSION 2.1 General lhe evaluation of the licensee's response was accompilshed by examir.ing the licensee's report for completeness and technical accuracy.

The licensee's report used in this evaluation is dated November 12, 1980, i

and includes the responses to the Bulletin Supplements Oith the exception of I/E Supplement No. 3 issued on October 24, 1980.

i

. 2.2 On-Site Inspections The on-site inspection, made on selected IE equipment, verified proper installation of equipmer.t. overall interface integrity, locatit a *-ith respect to f1 cad level for equipment inside the containment, and manu-facturers nameplate data. The manufacturer and model number from the nameplate data was compared to information given in the Component Evaluation Work Sheets (CES) to the licensee's report.

Components that were examined during the field inspection are identi-fied by an asterisk (*) in Attachment 1.

If any discrepancies were

.N I noted between the installed equipment and the correspondent equipment addressed in the licensee's report, they are discussed in Section 4 of this report. The site inspection is documented by IE report number i

50-348/80-38.

2.3 Evaluation of Licensee's Report Each compcnent as addressed on the Component Evaluation Work Sheets (CES) of the licensee's report was examined for completeness and accuracy to the criteria given in the bulletin.

This examination assumed qualification documents (analysis, test reports, etc.) referenced by the licensee in their submittal are acceptable.

1 i

~

. The results of this examination are documented in Attachment 1.

The CES page numbers in column 1 of Attachment 1 is the same CES page found in the licensee's report.

3.

GENERAL INFORE\\ TION 3.1 Identification Of Class 2 Electrical Equipment The licensee's list of systems was compared to the systems listed on.

This list is considered to be a standard list for pressurized water reactors.

It is recognized that there are differences in nomenclature of systems because of plant vintage and engineering design, therefore, many of these systems may not exist for Farley Unit 1 plant or the function of these systems for the Farley Unit 1 plant may be performed by comparable systems with different names. In any case, all the systems of Attach-ment 2 were not addressed or listed in the licensee's report. To insure completeness and unitormity of reports or similar design, it is considered that the licensee should address the following systems:

(1) Steam Dump (2) Containment Sump.

Each of the above systems should be analyzed and a brief discussion should explain how the system was addressed or why it was excluded from the report. For example: " Reactor Protection System - This is a

-~ -

~ -

4 valid system designation at Farley Unit 1 plant; however, the input signals to this system are obtained from various components in other systems that are included in this report."

3.2 Service Conditions The service condition accident environment, HELB/LOCA inside contain-ment and HELB outside containment are indicated or discussed in the licensee's report.

3.3 Qualification Documentation is a list of documents (test reports, analysis, letters, etc.) used by the licensee in determining the environmental qualifica-tion of plant equipment for Farley Unit 1.

These references have been tabulated by the licensee and are indicated on the applicable CES of their report.

4.

EQUIPMENT Lain REVIEW 4.1 Equipment that is cont,idered to meet IEB 79-01B requirements are categorized as 1 in the last column of Attachment 1.

4.2 Equipment whose qualified life (Aging) is less than the life of the plant is categorized as 2 in the last column of Attachment 1.

~

. 4.3 The licensee has identified specific equipment which has been or is being replaced, modified or relocated as a result of their IEB 79-01B efforts. This equipment is categorized as 3 in. the last column of A t ta c hir.e r.:

4.4. Equipment whose qualification is unresolved (such as, a qualification record search is still in process, tests are scheduled to determine qualification, additional information is needed by the NRC reviewer to satisfy him that equipment is qualified, etc.) is categorized as 4 in the last column of Attachment 1.

4.5 Equipment that the licensee has identified as not being qualified required an LER wth justification for continued plant operation.

No LER's were receive:d in Region II for Farley 1.

4.6 Equipment whose qualification (.\\ging exempted to a certain degree -

see DOR guideline Section 4) is unresolved, as identified by the licensee 1. listed in Attachment 4 as Gutstanding Items.

The licensee has provided justification for continued plant operation for many, if not all, of these outstanding items in their report. In many cases, this is provided on their CES or in a special section of the report. In some cases the licensee states that this justification is by Engineering Analysis that are available at their office.

i

. 4.7 The components reviewed during the on-site inspection were examined for proper installation, interface integrity, location and manufacturers nameplate data.

THe manufacturers nameplate data was compared to the

.:d m inon sr.c,n in tne compo m t a alma t ter. saeets ci the liunsee's Ri report.

The components that contained discrepancies between the actual nameplate data and the licensee's submittal to IEB 79-01B are identified by double asterisks (**) in Attachment 1.

However, these have been identified by the licensee as a result of a walkdown program initiated prior to the on-site inspection as indicated in their report, Section C.I.4.

5.

CONCLUSIONS Due to the time constraints imposed by the Commission Memo and Order of 5/23/80 this evaluation is based on the licensee submittal dated November 12, 1980. This licensee's report does not address all itees that may be pertinent to Farley Unit 1 plant as a result of IEB 79-01B Bulletin Supplements 2 and 3 issued on 9/30/80 and 10/24/80, respectively. Specifically, information en cold shutdown and TMI Lessons Learned related equipment which is received subsequent to 11/1/80 will be evaluated by EQB of NRR.

The licenssee's actions meet the requirements of the Commission Memo and Order of 5/23/80 and justification for continued plant operation with many of the components that have unresolved qualification items is indicated in Section 4.6.

Based on the information available, the Region II reviewer

.--.--p.

_7_

considers that the justification is commensurate for the areas identified, that the proposed corrective action meets requirements of the Commission Memo and Order of 5/23/80, and therefore, plant operation can continue unt:1 these items are resolved as committed to by the licensee.

This evaluation is based on the information supplied by the licensee in their submittal, their FSAR, and the assumption that the Qualification Documents (Test Reports, Analysis, Letter, etc. ) are 4.cceptable.

The results of thi:: evaluation does not necessarily imply that the equipment is unreliable, unsafe or represents a significant safety issue; it does imply that additional information is required.

This is indicated by the applicable categorization indicated in the last column of Attachment 1.

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