IR 05000387/1979009
| ML17138A641 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/18/1979 |
| From: | Jernigan E, Lester Tripp, Walton G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17138A640 | List: |
| References | |
| 50-387-79-09, 50-387-79-9, NUDOCS 7906260323 | |
| Download: ML17138A641 (10) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-387/79-09 Docket No.
50-387 License No.
CPPR-101 Priority l
Category A
Licensee:
Pennsylvania Power 5 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 r
Faci 1 ity Name..
Susquehanna Steam Electri c Station Inspection at.
Berwick, Pennsyl vania Inspectors:
Inspection conducted Feburary 27-28 and March 1-2, 1979 C'.
P. Jerniga, Reactor Inspector c g G. A. Walton, Reactor Inspector
~ '<Ci ate signed date signed Approved b
.
E. Tripp, Ch'ineering Support Section No. 1, R
S Branch date signed n
. date igne, Ins ection Summa.
Ins ection on Februar 27-28 and March 1-2, 1979 Re ort No. 50-387/79-09 A I":
R i, p
b
1 d
inspectors of activities associated with modifi'cations to feedwater nozzles and storage of safety related components.
The inspection involved 65 inspector-hours on-:site by two NRC regional based inspectors.
Results:
No items of noncompliance were'.sidentified.
Region I Form 12
. {Rev. April 77)
SOD>~~ >2
DETAILS Persons Contacted Penns lvania Power 8 Li ht Com an
- R. Beckley, Site gA Engineer E. Brignole, Engineer E. Carroll, Site gA Engineer J.
Green, Resident Nuclear gA Engineer
"A. Sabol, Manager, Nuclear guality Assurance
- Mr. Waldrop, Auditor
- W. Gulliver, Nuclear guality Assurance Engineer
- T. Oldenhage, Resident Engineer
- R. Featenry, Project Construction Manager United States Nuclear Re ulator Commission
- R. Gallo, Resident Reactor Inspector
- W. Raymond, Reactor Inspector
- R. Smith, Investigation Specialist General Electric Com an C. Roof, gC Representative
- T. Levasseur, Site gC Representative Bechtel Cor oration
- M. Drucker, guality Assurance Engineer
"A. Spielhagen, Project Field Engineer
- B. Ott, guality Control Engineer
- J. O'ullivan, Project Field Engineer
- H. Lilligh, Project guality Assurance Engineer
- G. Shrader, Project Field guality Control Engineer
- C. Tur nbow, Field Construction Manager
- denotes those present at the exit meeting.
Pl ant Tour The inspectors observed work activities in progress, completed work, and plant status in several areas of the plant during the tour.
The inspectors examined work items for any obvious defects or noncompliance with regulatory requirements.
Where more detailed inspection of an area was conducted, the inspection scope and findings are described in other paragraphs of this repor.
Feedwater Nozzle Safe-End Modification The licensee's NSSS contractor, General Electric, is replacing the feedwater nozzle safe-ends to allow installation of a new design feedwater sparger.
The following listed activities were examined and verified that they were being performed in accordance with ASME Section III, Summer 1976.Addenda, and Section XI, Summer 1975 Addenda.
Etch, measure, and mark cut off line.
This activity for one safe-end was witnessed by the inspector.
The contractor per-formed a water etch to locate the existing weld, then located cut line 1.500 inch away from the weld.
Cut off existing safe-end, and remove by machining all existing inconel plus
.06 inch minimum of base metal on the inside.
Replace by'elding with P-1 material the inconel removal area.
Liquid penetrant examine the area after inconel and base metal removal and after completion of weld replacement.
Machine new weld prep, liquid penetrant examine and install new safe-end.
The new safe-end is P-1 with 308L stainless cladding to accept the new feedwater sparger design.
No items of noncompliance were identified.
4.
Reactor Coolant Pressure Boundar and" Safet Related Pi in Weldin The following listed activities were examined and verified that they were being performed in accordance with Sections III and IX of the ASME B&PV Codes, PSAR Appendix D, and Bechtel guality Assurance Manual.
a.
~el dime Welding of joints DBB-104-1, FW-3, and DBA-101-1, FW-7.
, Welding of joints DBA-102-2, FW-2, and GBB-107-1, FW-13.
The inspector verified selected detailed drawings, welding procedures, filter metal certification, welder qualification, quality control documentation, weld appearance, welding vari-ables such as amperage, interpass temperature and nondestruc-tive tests as appropriat b.
Nondestructive Examination NDE Radiographs and liquid penetrant examination results of the following wel:d joints.
GBB-107-1, FH-13 DBB-101-1, FW-3 DBB-103-1, FW-3 DBB-120-.1, FW-9 DBB-117-1, FW-3 HBB-158-1, FM-2 VRR-B31-1, FH-A2 DCA-110-2, FH-2 DCA-108-1, FW-10 DCA-110-1, FW-1 DCA-110-1, FW-5 The inspector verified surface preparation/conditioning of selected welds, qualification of examiners and examination techniques.
No items of noncompliance were.identified.
5.
Installed Reactor Pressure Vessel RPV Protection The inspector examined protection provided the installed RPV and closure heads for compliance with applicable procedural require-ments.
The inspector reviewed the storage procedures and verified that periodic inspections,and preventive maintenance were being performed as specified.
The inspector verified that RPV nozzle openings were covered with plywood covers to prevent the entry of construction debris and protect the end-joint weld preparation.
The inspector also observed that an adequate protective enclosure had been constructed over the open RPV to provide for controlled access into the vesse The closure head was stored on dunnage and covered with a flame retardant material;.the component appeared to be free of rust.
The inspector verified that periodic inspection, as specified in the applicable procedure, had been made.
Documentation audited by the inspector-included the following:
Project Special Provisions SF/PSP G-5.1.
Field Inspection Procedure G-5.
Equipment Maintenance Requirement and Record Forms.
No items of noncompliance were identified.
6.
Protection of Stored RPV Internals The inspector examined protection of stored RPV internal components for compliance with site procedural requirements.
The inspector reviewed procedures specifying storage and protection for the RPV internals.
The inspector observed the in-plant storage/protection of the separator, shroud head and steam dryer.
The inspector verified that 'inspections required by specification had been con-ducted accordingly.
Documents audited by the inspector included:
Project Special Provisions Notice SF/PSP G-5.1.
Field Inspection Procedure G-5.
Equipment Maintenance Requirements and Record Forms.
No items of noncompliance were identified.
7.
Safet Related Com onents Observation of Work and Work Activities The inspector audited procedures to control the storage and pro-tection of certain safety related components.
The inspector also verified procedure implementation and audited associated records.
These audits and observations were made to determine if the estab-lished program and its implementation were consistent with the requirements of Appendix D of the PSA a.
Stora e, Handlin, and Protection The inspector toured safety related equipment storage areas which included:
(1) the off-site storage warehouse; (2) plant drywell; and, (3) reactor building.
The tour was conducted to determine whether storage requirements were being met relative to:
(1) protection; (2) identification; (3) nonconforming conditions identified; (4) lubrication; (5) preservation/heaters; (6) surveillance/maintenance activities.
The inspector observed that the warehouse provided protection and storage environment equal to that specified by the equip-ment supplier.
Additionally, the inspectors observed the storage/protection provided the recirculation system pumps and isolation valves, main steam isolation valves, residual heat removal pumps, core spray pumps and associated barrels.
No items of noncompliance were identified.
8.
Mana ement Meetin At the conclusion of the inspection on March 2, 1979, a meeting was held at the site with representatives of the licensee and contractor organizations.
Attendees at this meeting included personnel whose names are asterisked in Paragraph 1.
The inspector surmarized the purpose and results of the inspection as described in this report.