IR 05000387/1979019
| ML17138A843 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/11/1979 |
| From: | Durr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17138A839 | List: |
| References | |
| 50-387-79-19, NUDOCS 7910090667 | |
| Download: ML17138A843 (6) | |
Text
U. S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-387/79-19 Docket No. 50-387 License No.
CPPR-101 Priority:
Category:
A Licensee:
Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Facility Name:
Susquehanna Unit 1 Inspection at:
Berwick, Pennsylvania Inspection conducted:
May 15-18, 1979 Inspectors:
J.
P. Durr, Reactor Inspector ate signed Approved by:
L.
E. Tripp, Chief, Engineering Support Section No. 1, RC & ES Branch date, signed Ins ection Summar Unit 1 ins ection on Ma 15-18 1979 Re ort No. 50-387/79-19 Areas Ins ected:
A regional based inspector performed a routine, unannounced inspection of piping installation and documentation activi-ties.
The inspection involved 24.5 inspector-hours on site by one NRC inspector.
Results:
One item of noncompliance was identified in one of the two areas inspected (Infraction - Failure to provide the prescribed weld profile transition on safety-related piping, Paragraph 2).
DETAILS 1.
Persons Contacted a.
Penns lvania Power and Li ht Com an L. Ballard, Site gA, Engineer R. Beckley, Site gA Engineer
"S.
R.
Denson, Assistant Project Construction Manager
~E.
W. Elyard, Site gA Engineer
"R.
H. Featenby, Project Construction Manager
- "M. Gorski, Resident Engineer
~J.
D. Green, Resident Nuclear gA Engineer
~R. Stanley, Engineer b.
Bechtel Cor oration
~M. Daubenmeyer, Project Superintendent
"M. A. Drucker, Lead guality Assurance Engineer
"H.
F. Lilligh, Project guality Assurance Engineer
"T. Minor, Field Engineer
."W. Ross, Lead Field Welding Engineer
~G. Shrader, Project Field gC Engineer
'c.
NED
"T.
M. LeVasseur, guality Control Representive
~Denotes those persons present at the exit interview.
2.
Plant Tour The inspector toured the Unit 1 reactor building and the primary containment.
Installed piping and piping installation activities were examined.
The examinations included pipe weld fit-ups, alignments, welding, and completed installation quality.
The 20-inch diameter RHR to 28-inch diameter recirculation loop pipe weld DCA-108-1-FW-1 was examined for weld quality and appear-ance.
The weld profile does not satisfy the "Technical Specifica-tion for Field Fabrication and Installation of Nuclear Service Piping, M-204," Paragraph 6.2.3, in that it presents a severe notch at various locations on the toe of the weld.
Specifically, the edge of the weld on the "Tee" side, in the top quadrant has been installed such that the weld slopes downward from the elbow fitting to the "Tee."
The "Tee" weld preparation appears to have been machined to match a standard pipe wall.
The abutting elbow
f fitting, having a heavier wall, does not adequately match the outside diameter of the "Tee," therefore causing a reverse slope.
The weld has been completed, as evidenced by the welding documen-tation, WR-5, and final accepted.
The failure to provide the appropriate weld surface is an item of noncompliance (387/79-19-01).
3.
Reactor Coolant Pressure Boundar
- Review of'alit Documentation Seven nuclear class I pipe welds were selected for review to verify that portions of the ASME III Code, the guality Assurance Manual ASME Section III, and regulatory requirements were satis-fied.
The following weld documentation was reviewed:
Meld Identification DBA-102"1-FW-2 DCA-108"1-FW-6 DCA-110-1-FM"6 DCA-109-1-FW-1 DBA-101-2-FM-7 DBA-108-1-FW-8 DLA-104-1"FM-1
~Setem HPCI RHR RHR CS RWCU Nuclear Boiler FW Diameter 1pll 2pll 24" 12" 18"
I I 24ll Examination of the radiographs for weld DBA-108-1-FW-8 disclosed that view 10-11 had been rejected for sensitivity.
This was due to the inability to identify the "4T" hole in the penetrameter.
It appears that a transpositional error caused view 11-0 to be reshot by mistake.
Thus, there is no-.acceptable vtew, of.
lp-ll This item is unresolved pendi'ng a reshot of.at'ea,,
~10-11, and rev'iew 4y Ne, NRC (387/'79;19-.0ZJ;
-
.
No further discrepancies were identified.
Seven Nonconformance Reports were selected for review to determine retrieveability, trends, and adequate disposition.
NCR 3659 des-cribes a situation in which the cleanliness
"crawl through" inspec-tion of'he "B",recirculation loop was not performed.
The disposi-tion implies that a "crawl through" inspection was not mandatory.
It appears that the intent of the referenced GE Specification 22A-4628 was to perform cleanliness inspections in accordance with GE Specification 22A-2537.
The person responsible for these requirements was not availabl'e at the time of this inspection to provide the necessary information to resolve this matter.
This item is unresolved pending evaluation by the licensee and review by the NRC (387/79-19-03).
4.
Reactor Coolant Pressure Boundar
- Observation of Pi e Meldin The inspector observed the welding of the intermediate filler passes of the 12-inch diameter, nuclear class I, pipe joint OCA-107-01-FM-04.
He verified that the following attributes meet the applicable portions of the ASME III and IX Codes, the guality Assurance Manual ASME Section III, and regulatory requirements:
Melder qualification, weld identification, applicable weld procedure, specified weld material, weld deposit appearance, and quality control checks.
No items of noncompliance were identified.
5.
Unresolved Items Unresolved items are matters about which more information is
- 'equi,red to ascertain whether they are acceptable items,
.i'tems of noncompTi'ance-,
or deviations..
Unresolved items disclosed, dtIring',this inspection are discussed in Paragraph 3.
6.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on May 18, 1979.
He summarized the scope and findings of the inspectio ~(
V