ML20206Q761

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Forwards Equipment Qualification Insp Rept 50-382/86-32 on 861208-870313.Program Re Qualification of Electric Equipment Meets Requirements of 10CFR50.49.Seven Potential Enforcement/Unresolved Items Noted in Encl App a
ML20206Q761
Person / Time
Site: Waterford Entergy icon.png
Issue date: 04/16/1987
From: Gagliardo J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Dewease J
LOUISIANA POWER & LIGHT CO.
Shared Package
ML20206Q768 List:
References
NUDOCS 8704220032
Download: ML20206Q761 (5)


See also: IR 05000382/1986032

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In. Reply Refer To:

Docket: 50-382/86-32

License: NPF-38

Louisiana Power & Light Company

ATTN:

J. G. Dewease, Senior Vice President

Nuclear Operations

N-80

317 Baronne Street

New Orleans, Louisiana

70160

Dear Mr. Dewease:

SUBJECT:

EQUIPMENT QUALIFICATION INSPECTION - WATERFORD STEAM ELECTRIC

STATION,. UNIT 3

This refers to the first round special team inspection to review compliance

with 10 CFR 50.49, of activities authorized by License No. NPF-38, conducted by

Mr. A. R. Johnson and other NRC representatives, onsite during the period of

December 8-12, 1986, and subsequently at the NRC Region IV office until

March 13, 1987, concerning the Waterford Steam Electric Station, Unit 3.

The

team's findings were discussed with members of your staff at the conclusion of

the onsite inspection on December 12, 1986.

Areas examined during the inspection included your implementation of a program

for- establishing and maintaining the qualification of electric equipment within

the scope of 10 CFR 50.49.

In preparation for this inspection, the NRC team

included reviews and evaluations of your implementation of EQ corrective action

commitments identified in Safety Evaluation Reports (SERs) NUREG 0787,

Supplements 5, 8, and 10 (June 1983, December 1984, and March 1985), which were

satisfactorily accepted by the NRC staff at that time with regards to equipment

for which justification for interim operation (JI0s) were provided prior to the

November 30, 1985, deadline.

.

Within these areas, the inspection consisted of the examination of selected

procedures and records, interviews with personnel, and observations by the NRC

inspectors. The inspection findings are documented in the enclosed inspection

report.

'The inspection determined that you have implemented a program to meet the

requirements of 10 CFR 50.49. Seven deficiencies with respect to your program

implementation, involving EQ documentation files and physically installed

configurations of equipment in your plant, are summarized in Appendix A and are

classified as Potential Enforcement / Unresolved Items requiring further action.

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All seven Potential Enforcement / Unresolved Items represent failures to fully

establish the qualifications of the following equipment: Borg-Warner motor

operators ITT Barton.763/764 pressure transmitters, Okonite bolted cable

splices to General Electric pump motors, Thomas and Betts blind barrel crimp

cable spl_ ices to Limitorque SMB series motor operators, unidentified internal

wiring in Limitorque SMB series motor operators, and BIW cable assemblies.

Sixteen concerns are classified as Open. Items and a future NRC inspection'will

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review your actions concerning them.

Your . letter to NRC,, Region IV of February 2,1987, providing additional

information subsequent to the onsite inspection, addressing the. inspection

findings presented in~the exit interview on December 12, 1986, has been

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reviewed and was considered in preparation and issuance of the enclosad

inspection report.

-Your corrective actions regarding the identified deficiencies in the enclosed

inspection report should not be delayed pending a future NRC Region IV

inspection.

We are available to discuss any questions you have concerning this inspection.-

Sincerely,

Original Signed bkt

J. E. GAGLIARDO

J. E. Gagliardo, Chief

Reactor Projects Branch

Enclosures:

1.

Appendix A~- Potential Enforcement / Unresolved Items

2.

Appendix B - NRC Inspection Report

50-382/86-32

cc w/ enclosures:

-Louisiana Power & Light Company

'

ATTN:

G. E. Wuller, Nuclear

Services Licensing

P. O. Box B

.

Killona, Louisiana

70066

Louisiana Power & Light Company

-ATTN:

-N. S. Carns, Plant Manager - Nuclear

P. 0.' Box B

Killona, Louisiana

70066

4

Middle South Services

ATTN: Mr. R. T. Lally

.

P. O. Box 61000

New Orleans, Louisiana

70161

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Louisiana Power & Light Company

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' Louisiana Power & Light Company

ATTN:

K. W. Cook, Nuclear Support

and Licensing Manager

317 Baronne Street

P. O. Box 60340

New Orleans, Louisiana

70160

Louisiana Radiation Control Program Director

bec to DMB (A048)

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bec distrib. by RIV:-

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  • D.' Weiss, RM/ALF
  • RRI

R. D. Martin, RA

  • Section Chief (RPB/C)

DRSP

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  • RSB

D. Norman

  • RIV File.

J. Taylor, IE

  • A. Johnson

B. Grimes, DQAVT

U. Potapovs, IE, VPB

E. Herschoff, IE, VPB

  • SectionChief(RSB/ES)
  • 766

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APPENDIX A

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Potential Enforcement / Unresolved Items

= As a result of the special equipment qualification (EQ) inspection of

December 8-12, 1986, the following items have been identified by Region IV as

Potential. Enforcement / Unresolved Items (paragraph references are to the

detailed portions of the inspection report).

1.

Contrary to paragraph (f) of 10 CFR 50.49, the equipment qualification

file '(EQF), electrical equipment qualification documentation

package (EEQD) 42.3, for Borg-Warner motor operator model 39400 installed

in the containment building, did'not adequately establish qualifications

because of failure to demonstrate similarity.between the tested

model 86090 and the installed model 39400. Justification for Interim

Operation (JIO) for.Borg-Warner operators, dated May 16, 1985, required a

station modification to upgrade these operators by November 30, 1985,

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(paragraph 4.f.(1), ' Item 50-382/8632-01).

2.

Contrary to paragraph (f) of 10 CFR 50.49, the EQF,.EEQD 8.2A for ITT

Barton model 763 and 764 pressure transmitters during the time of the NRC

inspection, did not adequately establish qualification because of failure

to demonstrate qualification for submergence based on DBA/ post DBA

conditions.

(paragraph 4.f.(3), Item 50-382/8632-02).

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~3.

Contrary to paragraph (f)_of 10 CFR 50.49, the EQF for General Electric

CVC charging pump motors, did not adequately establish qualification

because of failure to demonstrate similarity between the type tested

- nuclear qualified heater connection splices and the installed Okonite

bolted type taped s lices at the Waterford plant-(paragraph 4.h.(2)c,

Item 50-382/8632-03 .

.

4.

Contrary to paragraph (f) and (k) of 10 CFR 50.49, and NUREG 0588,

Category II, paragraph 5, the EQF for Limitorque motor operator,

model.SMB-00, UNID No. EFW-MVAAA-220-A, did not adequately establish

qualification because of-failure to demonstrate similarity between the

tested and installed cable splices. No evidence was contained in the EQF

which could demonstrate qualification of blind barrel crimp splices used

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in operator EWF-HVAAA-220-A (paragraph 4.f.(4), Item 50-382/8632-04).

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Contrary to paragraphs (f) and (k) of 10 CFR 50.49, and NUREG 0588,

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Category II, paragraph 5, the EQF, EEQD 3.1, for model SMB series

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Limitorque motor operators did not adequately establish qualification of

~ internal wiring installed in operators prior to September 1986, in that

wiring was unidentified and there were no test reports to show that the

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wiring was qualified in accordance with 10 CFR 50.49 (paragraph 4.f.(6),

Item 50-382/8632-05).

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6.

Contrary to paragraphs (f) and (k) of 10 CFR 50.49, and NUREG-0588,

Category II, paragraph 1.2.(5), the EQF, EEQD 14.1/52.1, for BIW cable

assemblies (which includes CIR series connectors and flex conduit), did

not adequately establish qualification because it failed to base the

temperature qualification for materials within the connector / cable

assembly on the temperature effects of a MSLB as modified by a thermal lag

analysis (paragraph 4.f.(7)(a)

Item 50-382/8632-06).

7.

Contrary to paragraphs (f) and (k) of 10 CFR 50.49, and NUREG-0588

Category II, paragraph 4(2), the EQF, EEQD 14.1/52.1, for BIW cable

assemblies (which includes CIR series connectors and flex conduit), did

not adequately establish qualification because no replacement schedule had

been established for components susceptible to aging effects that are

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located in an elevated service temperature environment-

(paragraph 4.f.(7)(b), Item 50-382/8632-07).

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