ML19220B315
| ML19220B315 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/23/1977 |
| From: | Haynes R, Walton G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220B310 | List: |
| References | |
| 50-320-77-25, NUDOCS 7904250629 | |
| Download: ML19220B315 (6) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
77-25 Docket No.
50-320 Category B
License No.
CPP".6g Priority Licensee: _ Metropolitan Edison Comoany P. O. Box 542 Reading, Pennsv1vania 19603 Facility Name:
Threa File Island Unit 2 T--oection at:
Middletown, Pennsylvania Inspecu'mn conducted: Juna 14 - July 1 and July 11, 1977 Inspectors:
g/T44/m
/7,.-, _ J -7 /077 G. A. Walton, Reactor Inspector
/date Vigned S C h n a t a r-Chiaf. Enoinearino Suoport Section No. 2 RC&ES Branch date signed date signed Approved by:
/
/
/L, J u re 17 R. C. Haynes[Jhief, Engineering Support date signed Section Nd'.1, RC&ES Branch Inspection Sumary:
Inspection on June 14 - July 1, and July 11, 1977 (Recort No. 50-320/77-25)
Areas Inscected:
Special, announced inspection involving the performance of nondestructive examinations of Class I and II piping system welds to ascertain licensee compliance with the preservice examination requirements set forth in Section XI of the ASME Boiler and Pressure Vessel Code, Winter 1971 Addenda.
Nondastructive examinations were perfomed by HRC contractor personnel working under the direction of an NRC inspector. The inspection involved 835 inspector hours onsite by one NRC inspector and eight NRC contractor personnel.
Results: No items of noncompliac.ce were identified.
(
'id-d34 Region I Fom 12 (Rev. April 77) i304250 6'27
DETAILS 1.
Persons Contacted General Public Utilities Service Corcoration (GPU)
- Mr. S. Levin, Project Engineer
- Mr. J. Wright, Site QA Manager Gilbert Associates (GA)
- Mr. W. E. Reynolds, Baseline Inspection Program Manager Nuclear ineroy Services (Canam)
- Mr. F. T. Carr, Manager, Inservice Inspection
- Mr. L. A. Johnson, Program Manager, Inservice Inspection Babcock and Wilcox (B&W)
- Mr. L. C. Rogers, Site Manager
(
- Mr. C. M. Fletcher, Manager, Quality Control Systems
- Mr. H. C. Rush, Quality Control Systems
- Mr. S. Bushkill, Section Supervisor, Radiography Mt. Vernon, Ind.
Materials Consultants International, Inc. (MCI)
- Mr. D. Higginbothan - Level III NDE
- Mr. L. Parvin - Level II NDE
~
- denotes those present at exit interview 2.
Nondestructive Examination of Selected Pioe Welds a.
General Forty-one pipe welds in v'. ass I and II piping systems were nondestructively examined by NRC c;ntractor personnel to ascertain the licensee's compliance with the preservice examin-ation requirements set forth in Section XI of the ASME Boiler and Pressure Vessel Code, Winter 1971 Addenda.
No items of noncompliance were identified.
1 id.33S
~
3 The contractor, Materials Consultants International, Inc.
(MCI), performed ultrasonic, liquid penetrant and/or magnetic particle examinations of the selected welds in accordance with the test requirements of Section XI. These examinations were performed independent of, and subsequent to, the preservice examinations performed by the licensee's contractor, Conam.
The procedures and equipment used by MCI for their examina-tions were different from that used by Conam.
MCI test personnel performed their work under the direction of the NRC inspector.
The ultrasonic equipment used by MCI was calibrated at the
- National Bureau of Standards, Washington, D. C., and instru-ment sensitivity calibrations were performed on the same calibration blocks utilized for the licensee's examinations.
b.
Welds Examined The NRC inspector selected the welds to be examined.
Selec-tion criteria used considered the importance of the weld to reactor safety, weld accessibility (i.e., difficult to inspect welds were purposely included in the sample), and the type of weld so that the sample included a variety of materials, diameters, and thicknesses of both shop and field fabricated i
welds. Of the forty-one welds selected, thirty were in the reactor coolant pressure boundary (Class I).
The plant identification numbers for the welds selected and examined were as follows.
(1) Reactor Coolant System RC 168 RC 102 RC 107L RC 041 RC 113 RC 014L RC 111 RC 100 RC 123 RC 106 RC 038 RC 158 RC 112 RC 154BM RC 050 (2)
Decay Heat Removal System DH 058 DH 041 DH 039 DH 045 DH 049 DH 010 DH 124 Yd 3'16 i
4 (3)
Core Flood System CF 026 CF 009 CF 001 CF 012 CF 003 CF 021 (4) Make-Up System MU 048 MU 274 MU 085 MU 275 MU 231 MU 276 MU 234 MU 278 MU 239 MU 270 MU 252 MU 254 (5) Pr;ssure Surce Line SR 0080 c.
Ex'-ination Resul ts Set -ci walds inspected gave ultrasonic sigral responses which required further evaluation to determine disposition. They were: DH 010, DH 014, DH 039, DH 124, CF 026, CF 012, CF 009, CF 001, CF 003, CF 021, RC 014L and RC 107L.
Further evaluation of these welds was made by MCI and NRC by a review of the weld joint design and construction radiographs.
It was dett rmined that, with the exception of welds RC 014L and RC 107L a counterbore made on the inside surface to facilitate tit-up was the source of the ultrasonic reflectors.
This counterbore was verified by reviewing the radiographic film from tha construction inspections.
During the radiographic review by MCI of the above listed welds on the decay heat and cnre flood systems, anomalies were observed on the radiographs for welds CF 012, CF 026, and CF 021.
A further review was' made by the NRC inspector and Level III qualified personnel from Gereral Public Utilities and United Engineers and Constructers.
l This resiew indicated the following conditicns on the radiographs:
I e
5 CF 012 - Station Number 42 One film had a density chan 2 from root area to valve s
wall.
The matching film to this se'. did not show this density change.
The condition was due to film graininess and was not associated with weld defects.
CF 026 - Station Number 11 to 12 In this area there was a gradual density change from the root area to the valve wall.
This indicated a slight wall thickness variation.
Ultrasonic examination veri-fied the weld and adjacent base material exceeds minimum wall thicknas recui rements.
CF 026 - Station Number 1 to 2-In this area there were acceptable slag inclusions and a gradual density change (wall thickness variation).
However, minimum wall thickness requirements were met.
CF 021 - Station Number 'd to 3 There was a low area which appeared to come from surface removal by some mechanical means.
Density readings ranged from 3.18 to 3.27 within this low area. Adjacent to the low area the density readings were 2.78.
Ultra-sonic thickness measurements chow the wall thickne.s exceeds minimum requirements.
The three welds listed above did not show any rejectable defects when the ultrasonic examinations were performed by Conam or the retest by MCI. Also the wall thickness measure-ments performed using ultrasonics were acceptable.
Based on the numerous reviews by Canam, GPU, UE&C, and the
" Authorized Inspector" on the initial acceptance and the re-review by GPU, UE&C and NRC it was detennined these welds were acceptable.
RC 014L and RC 107L Welds RC 014L and RC 107L showed recordable indications in the weld area which required further evaluation.
The construction radiographs were not on s.te at the time of b
6 this inspection.
They were provided onsite from the piping fabricator's shop on July 11, 1977. The review of these radiographs confirmed discontinuities were present in the welds at the location of the ultrasonic reflectors.
The discontinuities are acceptable tt the acceotance standards as specified in the ASME B&P-Code,Section III.
3.
Exit Interview
^
The inspector met with licensee representatives (denoted in Para-graph 1) at the conclusion of the inspection on July 11, 1977. The inspector summar ized the scope and findings of the inspection.
The licent's acknowledged the inspector's findings.
i
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