IR 05000483/1989008

Insp Rept 50-483/89-08 on 890328-0515.No Violations Noted. Major Areas Inspected:Inservice Insp Activities,Including Review of Procedures,Observation of Work Activities & Review of Data

ML20247P208
Person / Time
Site:	Callaway
Issue date:	06/01/1989
From:	Danielson D, Jeffrey Jacobson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20247P205	List: IR 05000483/1989008 ML20247P200
References
50-483-89-08, 50-483-89-8, IEB-88-008, IEB-88-8, NUDOCS 8906060124
Download: ML20247P208 (6)

Text

__-_ _ _ - _ _ _ _ - _ . _ _ ._ . _ .

..

i~ A !y ,

'

s ,

6*F ,; ,

.

L U.S. NUCLEAR REGULATORY COMMISSION'

i REGION.III y

Report No.'50-483/89008(DRS)'-

Docket'No. 50-483 -License No. NPF-30'

Licensee: . Union' Electric Compan ' Post Office Box 149-Mail Code 400 St. Louis,-:MO 65166

. Facility Name: .Callaway Nuclear Plant Inspection At: Steedman, MO .65077

' Inspection' Conduct : March 28-30, April 17-20,'and May 15, 1989

,

,

.

-

MA

'

Inspector- . M. Ja son- 6 F9

] ./ -. ,

Date .

x ,.  : -fo r . - ./

' Approved By:v b. H 'Dani son, Chief 4 /Pf Materials and Processes Section Date'

Inspection Summary Inspection on Ma'rch.28-30,, April 17-20 and-May 15, 1989 (Report No. 50-483/89008(DRS))

Areas Inspected: Routine, announced safety. inspection of Inservice Inspection-(ISI) activities' including a review of procedures'(73052),' observation of work

'

activities-(73753), and review of data (73755). Also, licensee response to NRC Bulletin' No. 88-08 (92703).

Results: No violations or deviations were identifie Based on the.results of the inspection, the following licensee strengths were note'd:

• Management involvement and commitment to a quality ISI effort was

~

evident.-

• ISI personnel in general exhibited thorough knowledge of and dedication to their tasks.

i i

'8906060124 890601 PDR ADOCK0500g3 Q

I-

_ _

,

. . 1

-

..

.

DETAILS

1. Persons Contacted Union Electric Company f

+*J. M. Gloe, Supervising Engineer

• C. E. S11zewski, Supervising Engineer

+*S. L. McCracken, ISI Coordinator

• K. C. Schoolcraft, Q. A. Engineer

• M. O. McCrady, Training Supervisor

• T. Pettus, Engineer Nuclear Energy Systems {

G. Larson, Site Supervisor, Level III R. Dycus, Level II C. Silva, Level II Conam M. Gortemiller,i.evel TiI B. Marlow, Site Supervisor Westinghouse J. Raschiatorie, Site Coordinator

• Denotes those attending the exit meeting on April 20, 1989.

+ Denotes those participating in the telephone exit on May 15, 198 . Licensee Action on NRC Bulletin No. 88-08 (92703)

This bulletin was issued to provide information related to piping failures caused by theraal fatigue. Thermal stratification in essentially stagnant piping induced unacceptable stresses which ultimately led to crackin Licensee's were asked to review any unisolable piping susceptible to i intrusion by coolant with a significant temperature differentia In response to the bulletin, the licensee identified a portion of the l CVCS piping with the potential for thermal stratification. Field welds FW-62, FW-63, FW-67 and the elbow upstream of 2-BG-24-FW68 on the auxilliary spray line were radiographer to rule out the possibility of cracking. The NRC inspector reviewed the radiographs and agreed with the licensee that no sign of cracking was apparent.

I

_ _ _ _ - _ _ _ _ _ _ _

._ _ --- - _ __ --- _ _ ____

g L .

-

..

I -

, Inservice Inspection - Ultrasonic Examination (UT)'

l General l .This examination was conducted as the licensee's first interval, l second period, first outage inservice inspection (ISI). The examination was performed by Nuclear Energy Systems (NES). Various liquid penetrant (LP) and magnetic particle (MT) examinations were also performed by NES. The ISI was performed in accordance with l ASME Section XI, 1980 edition with Winter 1981 Addend Procedure Review and Personnel Qualification (73052)

The NRC inspector reviewed the following NES procedures:

Title No./ Revision Liquid Penetrant Examination 83A1009, Revision 7 Ultrasonic Examination (General) 83A1005, Revision 5 Magnetic Particle Examination 83A1010, Revision 8 UT for RPV Stud Hole Threads and Closure Head Nuts 83A1025, Revision 1 UT of Studs from Heater Hole 83A1020, Revision 4 UT for Austenitic Piping Welds 83A1006, Revision 5 UT for Ferritic Piping Welds 83A1007, Revision 3 All procedures were found to be in accordance with applicable codes, standards and licensee commitment The NRC inspector reviewed the following NES personnel certifications:

C. Silva R. Dycus S. Larson C. Blum A. Porter D. Sells W. Downs The certifications were found to be in accordance with SNT-TC-1A

" Recommended Practice" of the ASNT and were acceptable, Observation of Work Activities (73753)

The NRC inspector verified that the following activities were performed in accordance with the Technical Specifications, licensee procedures, and applicable codes and standards:

- - - _ - - _ _ _ - _ _ _ _ _ - _ - _

_ _ _ _ _ _ _ - _ - _ _ - _ . _ _ _ _ _ _ _ _ _ _ _ - _ _ - - _ _ _ _ _ _ - _ _ _ _ _ __ .__ _ _ _ _ _ _ _ _ _ - ___-_

-

..

+

-

(1).' Calibration of equipment and both axial and circumferential scanning of the Class 2 Containment Spray System weld No. EN01-F01 (2). Calibration of equipment and scanning of the "B" steam generator main steam welds No. AB01-FW (3). Calibration of. equipment and UT examination of the reactor closure head nuts utilizing both 0* and 38" transducer (4). MT examination of reactor closure head stud Review and Evaluation of Data (73755)

The NRC inspector verified that the reported data covered the scope of examinations required during this inspection period as described in the ASME Code, Technical Specifications, and the license's ISI program. The following data was reviewed:

System / Component Weld /Compor.ent Containment. Spray "A" F017,F001 Containment Spray "B" F005, F009, S003-A CVCS Letdown S002-A RCP "D" Sea 1 water Injection FW 270, FW 271, FW 411, FW 410 Feedwater (loop 2) S026-A, F033, S026-B, S026-C Steam Generator "C" Hot and Cold Leg nozzle inner radius and channel head wel Steam Generators Hold down bolts'

RPV Closure Head Studs The data was found to be complete and well documented. .The evaluations were considered to be conservative and acceptabl . Inservice Inspection - Eddy Current Examination General The Callaway steam generators are Westinghouse Model In addition to the 100% pre-service inspection, three partial inspections have been performed prior to this outage. Specific concerns to date include anti-vibration bar (AVB) wear, tubesheet denting, support i

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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

'

.

. .

%'

..

plate denting, and IGSCC in the area of the flow distribution baffle-cutout. Tubes at the Callaway facility are examined over the full length, from tube end-cold to tube end-hot. The evaluation cf data for this examination was subject to three separate, independent analysis. . The primary vendor (Conam) was-responsible for both th primary and secondary analysis while Westinghouse parformed the third party analysis.' All personnel involved with the acquisition

.

and interpretation of eddy current data were qualified to the

" Recommended Practice" SNT-TC-1A 1975 and-1980 editions of the ASN Procedure Review and Personnel Qualification (73052)

The NRC inspector reviewed the following Conam procedures:

Title No./ Revision Multifrequency Eddy Current Procedure ETP-22-01300, Revision 0 Motorized Rotating Probe Procedure ETP-BB-01311, Revision 0 Eddy Current Testing Acquisition and Analysis Guidelines ETP-BB-1309, Revision 0 All procedures were found to be in accordance with applicable codes, standards and licensee commitment Personnel certifications for both Conam and Westinghouse staff were reviewed by the NRC inspector and found to be acceptabl Data Acquisition and Analysis (73755)

The NRC inspector observed eddy current data acquisition for the "B" and "C" steam generators. The remote probe manipulation and data recording operation was found to be in accordance with approved procedure The Zetec CDS automated analysis system was utilized by Conam for the secondary analysis. The final evaluations of eddy current indications performed by the licensee's contractors were judged to be conservative and acceptable. The examination resulted in the plugging of 4 tubes on "B:" steam generator and 9 tubes on "C" steam generator. All plugging was due to AVB indications except for one distorted signal at a baffl . Inservice Inspection - Reactor Pressure Vessel (73755)

l An underwater remote visual examination (VT-3) was performed in accordance with the requirements of ASME Section XI, 1980 Edition l

5

_ _ - _ _ - - _ _ _

, . - - - - - - - - - . . ___

l~s l s

.-

[. -

.

through the Winter, 1981 Addenda and the Licensee's Examination Pla The following areas were included in the examination:

Reactor Vessel Flange Mating Surface Upper Support Ledge Closure Head Location Pin Keyways Outlet Nozzle Bores l

l The NRC inspector reviewed a video tape of the examination and found it acceptabl . Exit Interview (30703)

l l The inspector met with site representatives (denoted in Paragraph 1) at the conclusion of the inspection. The inspector summarized the scope and findings of the inspection noted in this report. The inspector also-discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspector durii.g the inspection. The licensee did not identify any such documents /processess as proprietary.

I l

!

)

1

_ _ _ _ _ _ - - - - - _ _ - - - - - - - 1