Text

Forwards Insp Rept 50-416/86-30 on 860915-19.No Violations or Deviations Noted
	ML20214Q345
Person / Time
Site:	Grand Gulf
Issue date:	11/03/1986
From:	Verrelli D; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Kingsley O; MISSISSIPPI POWER & LIGHT CO.
Shared Package
ML20214Q348	List: IR 05000416/1986033; ML20214Q345;
References
	NUDOCS 8612050111
	Download: ML20214Q345 (2)
	v • d • e

w a-.= f

9 , _.

I

NOV 3 1986

Docket No. 50-416

License No. NPF-29

Mississkpi Power and Light Company

ATTN:vHr. O. D. Kingsley, Jr.

Vice President, Nuclear Operations

P. O. Box 23054 ,

'

Jackson, MS 39205

Gentlemen:

~

SUBJECT: NRC INSPECTION REPORT NO. 50-416/86-30

This refers to the f;uclear Regulatory Commission (NRC) inspection conducted by

J. L. Mathis on September 15-19, 1986. The inspection included a review of

activities authorized for your Grand Gulf facility. At the conclusion of the

inspection, the findings were discussed with those members of your staff

identified in the enclosed inspection report.

Areas examined during the inspection are identified in the report. Within these

areas, the inspection consisted of selective examinations of procedures and

representative records, interviews with personnel, and observation of activities

in progress.

Within the scope of the inspection, no violations or deviations were identified.

In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2,

Title 10, Code of Federal Regulations, a copy of this letter and its enclosure-

will be placed in the NRC Public Document Room.

Should you have any questions concerning this letter, please contact us.

Sincerely, .

1

S\

David M. Verre11i, Chief

Reactor Projects Branch 2

Division of Reactor Projects

Enclosure:

NRC Inspection Report

cc w/ enc 1: (See page 2)

8612050111' 861103 ~

PDR ADOCK 05000416 ,

G PDR 1

j

.

. , ' ..

" '

-NOV 3 1986

Mississippi Power and Light Company- 2

'

.j cp w/ encl:

V.H.Cloninger,VicePresident, Nuclear

Engineering and Support

v'fJj E. Cross, GGNS Site Director

W . R. Hutchinson, GGNS General Manager

v4.. F. Dale, Director, Nuclear Licensing

and Safety

/R.T.Lally,ManagerofQualityAssurance

Middle South Services, Inc.

/R. B. McGehee, Esquire

Wise, Carter, Child, Steen and Caraway

[N. S. Reynolds Esquire

Bishop, Liberman, Cook, Purcell

/ & Reynolds

vr R. W. Jackson, Project Engineer

4

)cc w/ encl:

ARC Resident Inspector

Document Control Desk

State of Mississippi

.

oley J lake AHerdt HDance

{f10/f//86 -10/gf/86

/ 10/y/86 10/)s/86

-

.

=

UNITED STATES

-[pato

.

'

o

o NUCLEAR REGULATORY COMMISSION

REGION 11 - .

f[ '

-

n.

y- j 101 MARIETTA STREET.N.W.

2 ATLANTA, GEORGI A 30323

%*,..*/ -

.

Report.No.: 50-416/86-33

s

Licensee: Mississippi Power and Light Company

,< Jackson, MS 39205,

Dacket No.: 50-416 License No.: NPF-29

Facility Name: Grand Gulf

-

4

Inspection Conduct 'd: S tember 29 - October 3, 1986 s

Inspec 'r : jpnMs- '

/6',Pf /d

ate &fgned

J. LT - ey g

l

-

J.J.- aL M Tn E be rie

Engineering Branch

j - Division of Reactor Safety i

SUMMARY

i

Scope: This routine, announced inspection was conducted . in the areas of

inservice inspection, review of procedures, observation of work and work activi-

ties, and data review and evaluation.

Results: No violations or deviations were identified.

l

!

i

,

a

4

n 2

o 4

~

,I

. v g -1

-

I

_ . _ _ _ _ . _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _____________._______________________._______.________,._____.___.t .

_ _ _ - _- . . ._

.. .

l-

. *

'

REPORT DETAILS

i

'

1. Persons Contacted

, Licensee Employees-

"

C. R. Hutchinson, Grand Gulf Nuclear Station, General Manager

i "L. F. Daughtery, Compliance Superintendent

J. E. Reaves, Quality Assurance Duty Manager

R. A. Courtney, Quality Assurance Supervisor

R. S. Lewis, Nuclear Plant Engineer

J. D. Bailey, Compliance Coordinator

,

Other licensee employees contacted included engineers, technicians,

'

mechanics, security force members, and office personnel.

1

- NRC Resident Inspector

j *W. F. Smith, Resident Inspector

Attended exit interview

2. Exit Interview

l The inspection scope and findings were summarized on October 3,1986, with

j those persons indicated in paragraph 1 above. The inspector described the

i

areas inspected and discussed in de tai.1 the inspection findings. No

l' dissenting comments were received from the licensee-. The following new item

i was identified during this inspection.

3

-

Inspector Followup Item 416/86-33-01, Administrative Corrections Needed

For Radiographic Procedure No. M-RT-XG-2, Revision 1.

1

The licensee did not identify as proprietary any of the materials provided'

to or reviewed by the inspector during this inspection.

3. Licensee Action on Previous Enforcement Matters

,

This subject was not addressed in the inspection.

4. Unresolved Items

Unresolved items were not identified during the inspection.

> 5. Inservice Inspection (ISI) - Review of Procedures (73052)'(Unit 1)~

]

i

The inspector reviewed the licensee's approved ISI program for the first 10

year interval ~. The program was. written to comply- with the ASME Boiler and

Pressure Vessel (B&PV) Code,Section XI,1977 Edition with Addenda through

,

r

, - - , - - - - ~ , - - - . ~ -m ,

-

.

. .

2

the Summer 1979.

The licensee is presently in the first refueling outage of the first period.

General Electric (GE) Apparatus and Engineering Services is performing the

Ultrasonic examinations of components and piping using . licensee approved GE

-

procedures. U.S. Testing was performing the required surfaces examinations

in accordance with Mississippi Power and Light's (MP&L) program and proce-

dures, and MP&L was performing the required visual examinations,

a. The following programmatic precedure and manuals were reviewed to

determine if they ware consistent with regulatory requirements and

licensee commitments:

MP&L's Inservice Inspection Ten Year Program

-

General Electric's Quality Assurance Manual for Inservice. Inspec-

tion Services for Grand Gulf 1 & 2 (QAM-3 Revision 10)

-

General Electric Apparatus and Engineering Services Procedure for )

Quality Assurance Indoctrination and Training (QA-1, Revision 0)

-

General Electric Apparatus and Engineering Services Procedure for

Qualification and Certification of Non-Destructive Examination

Personnel (QC-2 Revision 4)

-

Nondestructive Examination Turnover Request for the First.

Refueling Outage (Outage Plan)

b. The following GE Procedures were reviewed in the. areas of procedural

approval requirements for qualification of NDE personnel and compila-

tien of requiced records:

-

Procedure for UT Examination of Pressure Vessel Welds (UT-1, Rev.

1)

-

Procedure for UT Examination of Threads in RPV Flange (UT-6, Rev.

1)

-

Procedure for Remote. Ultrasonic Examination of Reactor Pressure

Vessel Welds and Base Material (UT-9,-Rev. 1)

-

Remote UT Examination of Nozzle to Vessel Welds (UT-10, Rev. 1)

-

Procedure for Evaluation of Ultrasonic Indications in Reactor

Pressure Vessel Welds (UT1.11.3, Rev. 0)

-

Procedure for UT Examination of Nuclear Piping Systems (UT-14,

Rev. 1)

-

Procedure for Manual Ultrasonic Examination of CRC Welds (UT-20,

Rev. 2)

.

k

%.

.~. . ._ - . . - .. .- . . - - - . . . -

-

.

' . .. .

>

. 3 -

..

,

-

Procedure -for UT Examination -of Pressure' Retaining Bolting

Exceeding Two Inches in Diameter (UT-21, Rev 1)

-

Procedure for Nozzle Inner Radius - Remote Ultrasonic Examination

}. (UT-28, Rev. 1)

-

Procedure for Ultrasonic Examination of Austenitic Metal Welds of

IGSCC (UT-30, Rev. 14)

-

Ultrasonic Planar Flaw Sizing (UT1.35, Rev. 3)

-

Procedure for Ultrasonic Examination of Pipe Welds Using Automated

Equipment (UT-43, Rev. 8)

!

'

-

Procedure for Ultrasonic Examination of Recirculation Piping Caps

for IGSCC (UT-46, Rev. 1)

.

. -

Procedure for Automated Ultrasonic Examination of CRC Welds

j (UT-47, Rev. 1)

4

j

'

-

Procedure for Automated Ultrasonic Examination of Dissimilar Metal.

Welds (UT-51, Rev.1)

-

Procedure for Ultrasonic Examination of Dissimilar Metal Welds

(UT-53, Rev. 0)

-

Ultrasonic Examination of Nozzle Inner ~ Radius -for Nozzles with

Inside Diameter of Less Than Ten Inches (UT-54, Rev. 0)

!

-

Procedure for Ultrasonic Examination of Jet Pump Beams.for Middle

. South Energy, Inc. , MP&L (09-08, Rev. 0)

-

' Review Process and Analysis of Recorded Indications (NDE-1, Rev.

. 0)

l

-

Procedure for Zero Reference Location and Data Recording for

i Non-Destructive Examination (NDE-49, Rev. 0)-

,

l c. The following GE and MP&L procedures were reviewed for- technical-

content and to determine if they were' consistent with the requirements

of the ASME, B&PV Code.

GE Procedure for Remote Ultrasonic Examination of Reactor Pressure

~

-

Vessel Welds and Base Material (UT-9, Rev. 1)

-

GE Remote UT Examination of Nozzle'to Vessel' Welds (UT-10, Rev. 1)

-

.

1

-

-GE Procedure for Nozzle Inner Radius Remote Ultrasonic Examination

(UT-28, Rev. 1)

-

s

i , .

L._,_.__.... . ___ _ ,. .,,_...a .; , . , _, _ . - , , .

- _ ..

. * j

. *

4'

-

GE Procedure for Ultrasonic Examination of Pipe Weld using

Automated Equipment (UT-43, Rev. 8)

! -

MP&L Quality Assurance Procedure Liquid Penetrant Examination

i . (QAP.9.50, Rev. 0)

.

-

MP&L Quality Assurance Procedure Magnetic Particle Examination

_ (Yoke Method) (QAP9.60)

'.

-

MP&L Nondestructive Examination Standard for. Radiography

(M-RT-XG-2, Rev. 1)

During the inspector's review of MP&L's radiographic procedure

M-RT-XG-2, Rev. 1, the following administrative errors were noted:

'

(1) The scope of the docum2nt (paragraph 1.2) identified that this

standard was written to comply with the ASME B&PV Code,Section V,

Article 2, 1974 Edition including Addenda through Summer 1974.

.

The ISI program requirements for radiographic examination is the

ASME B&PV Code,Section V and XI Article 2, 1977 Edition including

i Addenda through Summer 1979, however, the inspectors review of the i

i procedure did not identify any technical requirement that would

! not meet the 1977 Code. The licensee should update the scope of

4

the document to include the 1974 Construction Code and the 1977

i ISI 10 year interval Code prior to its use in the program.

!

(2) Paragraph 3.0, entitled, " Equipment, Materials and Pe'rsonnel,"

should describe the method used to determine actual effective

source size. Attachment 1 (Radiographic' Technique Sheet), depicts

the actual source size being derived from a formula. However, the

,

cadiographic procedure does not identify the values- to be used in

1

the formula.

(3) Paragraph 4.6.2 has a typographical error that changed the

acceptance criteria for geometrical unsharpness from .070 inch to

,'

.70 inch for material thicker than 4 inches. A Boiling Water

Reactor like Grand Gulf, however, does not have materials thicker

than 4 inches with the exception of some portions of the reactor

i vessel.

I

The inspector identified the above administrative'~ concerns as Inspector

Followup Item 416/86-33-01, Administrative Corrections Needed for

Radiographic Procedure No. M-RT-XG-2,' Revision 1.

Within the areas examined, no violations or deviaticns were identified.

,

i

l

,

'

_ _ .. . . - _ . ---

-._

.

. .

5

6. Inservice Inspection - Observation of Work and Work' Activities (73753)

'(Unit'1)

The inspector observed the ISI activities described below to determine

whether these activities were being performed in accordance with regulatory

requirements and licensee procedures. See paragraph 5 above for the

applicable code.

a. Examiner Qualification

The ' inspector reviewed the qualification -documentation for the below

listed examiners in the following areas: employer's name; - person

certified; activity qualified to perform; effective period of certifi-

cation; signature of employer's designated representatives; basis used

for certification; and annual visual acuity, color vision examination

and periodic-recertification.

Examiner Method Level

T. White UT II

P. Ramsey UT III

A. Clay UT III

R. Anderson UT II

F. Witherspoon UT II

S. Whiddon UT II

M. Sessoms UT II

R. Lindeman UT III

B. Dummer UT II

b. In process ultrasonic examinations (UT) of the recirculation system 12

inch diameter riser pipe welds listed .below were' observed by the

inspector. The examination of these welds was conducted by Gen,eral

Electric using SMART automated ultrasonic system.

Weld No. Component Configuration Calibration Sheet No.

G-11-B206A Elbow to Pipe. 862012/862011

G-001 W40 Pipe to Safe-end 862507-

G-11-8231-B Elbow to Pipe 862505

The above UT examinations including calibrations were compared with the

requirements of: the applicable procedure and code in the following

areas:

-

Availability of and compliance with approved NDE procedures l

-

Use of knowledgeable NDE personnel l

-

'Use of NDE personnel qualified to the proper leve,1 '

-

Recording of inspection results

l

-f

.

- ,

- , ._- - . ~ . - -. , - - ,. _ ,,_._,. -.. , , .

-".--.,. l

<';- p

.. . .j

. ..

6

.

-

Type of apparatus used

-

Extent of coverage of weldment

-

Calibration requirements

-

Search unit'

-

Beam angles

-

DAC curves

-

Reference level for monitoring discontinuities

-

Method of demonstration of penetration

-

Limits of evaluating and recording in'dications

-

Recording significant indications

-

Acceptance limits

c. In process UT calibration and crawler positioning for reactor vessel

circumferential weld A-B was observed, by the inspector. The UT

examination of this vessel weld was performed with an automated remote

ultrasonic system which presents the data in a digitize form. This-

system is normally referred to as the GE Blue Boy System. The name.has

been derived from the enclosure that houses the system. -The six

channel calibrations were compared with the requirements of the

applicable procedure and code as described-in paragraph-b. above.

Within the areas examined, no violation or deviations was identified.

7. Inservice Inspection, Data Review and Evaluation,' Unit 1 (73755) 4

The inspector reviewed UT . data which included computer disc and VCR tapes

that had been evaluated by GE examiners. However, - thi s data was not

considered completed data since GE's evaluation required in many situations

that supplemental examinations be performed. -The inspectorf reviewed the

data to ascertain whether the methods, techniques and extent of the examina-

tion complied with the ISI plan and applicable NDE procedures; findings were

properly evaluated by qualified personnel; and programmatic-deviations were

-

recorded as required. Records for the following welds were reviewed:

Weld No. System Size- Evaluation Status

G11-8206A Recirculation 12" Diam. Requires Further

Evaluation Utilizing

Manual UT

G11-A26-B Recirculation 12" Diam. Requires Further

Evaluation Utilizing

Manual UT

G11-8282-A- Recirculation 12" Diam.

'

Requires Further !

Evaluation Utilizing l

Manual UT-

G-11-A51-B Recirculation 12" Diam. Requires Further

' Evaluation Utilizing l

Manual UT

- -

1

-

'

.

, . .

ir:' ' :g,37

-

I

fj es . ^

,

. . .

7

G11-8333-A Recirculation 12" Diam. Satisfactory

G11-A102-A , Recirculation 12" Diam.

-

Satisfactory

G11-A26-A Recirculation 12" Diam. Sati sfactory

G11-8257-B Recirculation 12" Diam. Sati s factory

~A-B Reactor Vessel 100% Satisfactory

Weld

Nozzle B3-B Vessel to Nozzle 100% Satisfactory

Within this area of examination, no violation or deviations was identified.

'

.

e

J

)

ML20214Q345

Text

Navigation menu

Search