IR 05000320/1979024
| ML19308B306 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 10/09/1979 |
| From: | Lester Tripp, Walton G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19308B303 | List: |
| References | |
| 50-320-79-24, NUDOCS 7912280342 | |
| Download: ML19308B306 (3) | |
Text
.
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-320/79-24 Docket No.
50-320 License No.
DPR-73 Priority Category C
--
Licensee:
Metropolitan Edison Company P. O. Box 542
.
Readino. Pennsylvania 19603 Facility Name:
Three Mile Island Unit 2 Inspection at:
Milstead Boiler Co., Lynchburg, Virginia Inspection conducted:
September 5-6, 1979 Inspectors:
J/ %kNm
[r'- f'l iil 17
'G.' Walton, Reactor Inspector
~'dat'e signed date signed
,;
date signed Approved by: f-
[_
/#['/[7'[
a.. trippt, Lnlet, tngineering dupport Section date signed No.1, RC&ES Branch Inspection Summary:
Inspection on September 5-6,1979 (Report No. 59-320/79-24)
Areas Inspected: Special, announced inspection by regional based inspector of the fabrication and testing of the mini-decay heat removal system.
The inspection involved 14 inspector-hours by one NRC regional based inspector.
Results:
No items of noncompliance or deviations were issued.
Region I Form 12 7 S.12 2 80 3y7 (Rev. April 77)
. _ - _ _ _ _
..
DETAILS 1.
Persons Contacted General Public Utilities J. Bansch, Quality Assurance
,
Babcock & Wilcox Company S. Brown, Lead Mechanical Engineer D. Kalen, Lead Design Engineer C. Pollard, TMI-2 Site Team Member R. Fair, Quality Assurance Inspector G. Skillman, Engineering Operations Manager Milstead Boiler Company C. Phelps, Certified Welder H. Taylor, Shop Foreman Kemper Insurance Canpany F. Araujo, Authorized Nuclear Inspector 2.
Mini-Decay Heat Removal System The inspector audited the fabrication of the mini-decay removal system at Milstead Boiler Company, Lynchburg, Virginia. The system is fabricated to be used to cool the reactor core for up to three years. The system consists of pumps, heat exchangers, valves, and piping to be installed in parallel with the existing decay heat system and in parallel with the Westinghouse designed alternate decay heat removal system. The system will be used to remove decay heat from the reactor core until full defueling has been performed. The inspector audited the following items for canpliance with the applicable code, ANSI B31.1.
a.
Rerating Heat Exchangers The heat exchangers used were fabricated by Atlas Industrial Manu-facturing Company for use at Virginia Electric Power Company, North Anna, Unit 3.
The heat exchangers wore fabricated and calculated
to operate at 150 psig at 200 F.
The tubeside of the heat exchangers
were revised to operate at 235 psig at 200 F..
.
New code calculations, nozzle loading analysis, drawing revisions, and revised code stamping were made.
A Certificate of Compliance Form R-1 was issued by the Authorized Nuclear Inspector.
i b.
Welding Procedure Specification, Welder and Procedure Qualifications The inspector reviewed welding procedure specification number 8179-7506, Rev. O, supporting procedure specification 8179-7506, Rev. 2, dated August 15, 1979, and welder qualification for compliance with Section IX of the ASME B&PV Code.
The welding was qualified using "GTAW" gas tungsten arc welding, manual weld deposit with helium backing gas. The test sample was examined by tensile and guided bend test. The welder was qualified in the 6 G position.
c.
Hydrostatic Test
,
The inspector witnessed the hydrostatic test performed for compliance with ANSI B31.1.
All welds (with the exception of two welds on the outboard side of valves MDH-14 and MDH-17) were pressure tested at 352.5 psig for more than 10 minutes.
Pressure measurements were accomplished using heise gage which was calibrated September 2,1979.
-
The hydrostatic test was performed at 1.5 times design operating pressure (1.5 X 235 = 352.5). The hydrostatic test was in compliance with ANSI B31.1 and no leaks were observed in the welds.
In addition to the witness performed by the NRC, Quality Assurance inspectors from General Public Utilities, Babcock & Wilcox Company and the Authorized Nuclear Inspector witnessed the test.
d.
Visual Exmninations The inspector reviewed the documentation for visual examination for compliance with the applicable Code B31.1. The certification states the welds were examined and accepted by Quality Assurance inspectors from General Public Utilities and Babcock and Wilcox Company.
All areas reviewed by the inspector met the licensee's commitments and no items of noncompliance were identified.
3.
Exit Interview
,
At the conclusion of the inspection, the inspector discussed the inspection findings with representatives from General Public Utilities and Babcock &
,
Wilcox Caupany.
'
.
I