IR 05000387/1978023
| ML17138A519 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 01/11/1979 |
| From: | Gallo R, Mcgaughy R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17138A518 | List: |
| References | |
| 50-387-78-23, 50-388-78-20, NUDOCS 7903080002 | |
| Download: ML17138A519 (11) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT 50-387/78-23 R I II 50-387 Docket Ho.
50-.388 CPPR-101 License No.
CPPR-102 Region I Priority Category Licensee:
Penns lvania Power and Li ht Com an 2 North Ninth Street Allentown, Penns lvania 18101 Facility Name:
Sus uehanna Steam Electric Station, Units
and
Inspection at:
Berwick, Pennsylvania, Inspection conducted:
December 4-22, 197
~(. -M
~.,
.s, R. H. Gallo, Resident Rea d'or Inspector
/// 7/
date signed date signed Approved by:
! ',!!!E R.
l. McGaughyg ef, Projects Section, RCEES Branc'C date signed
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da sijned'
Ins ection Summar
Ins ection on December 4-22, 1978 Combined Re ort Nos.
50-387/78-23 and 50-388 78-20 Unit 1 Areas Ins ected:
Routine inspection by the resident inspector of work activities relative to:
installation and welding of reactor coolant pressure boundary and other piping; installation of 'reactor vessel internals; storage of reactor vessel and internals; and fire prevention/protection.
The inspector also performed plant tours and reviewed licensee action on previously identified items.
The inspection involved 59 inspector-hours by the NRC resident inspector.
Results:
No items of noncompliance were identified.
Region I Form
(Rev. April 77)
7803080 ~C W
~<
spection Summary I
Unit 2 Areas Ins ected:
Routine inspection by the resident inspector of work activities relative to:
storage of the reactor vessel and reactor vessel internals; and installation of containment penetrations.
The inspector also performed plant tours and reviewed licensee action on previously identified items.
The inspection involved 12 inspector-hours by the NRC resident inspector.
Results:
flo items of noncompliance were identifie DETAILS Persons Contacted Penns lvania Power'and Li ht Com an L.
R.
G.
P.
E.
S.
R.
J.
T.
R.
A.
Ballard, Site QAE Beckley, Site QAE Buvvis, Site QAE Capotosto, Site QAE Carroll, Site QAE L. Denson, Assistant Project Construction Manager - 1,
H. Featenby, Project Construction Manager -
Green, Resident NQA - 1, 2,
F. Oldenhage, Resident Engineer -
Prego, Site QAE R. Sabol, Manager, Nuclear Quality Assurance Bechtel Cor ovation M.
M.
M.
G.
G.
J.
A.
R.
H:
J.
B.
G.
A.
K.
C.
K. Boone, Lead Welding Engineer L. Daubenheyer, Project Superintendent Services A. Druckev, Electrical QAE - 1, 2,
Gallandorm, Lead Pipe/Mechanical Engineer Gelinas, QC Lead Engineer Piping/Mechanical Khandar, Mechanical QAE Konjura, Mechanical QAE Lamb, Assistant Lead Welding QCE Lil:ligh, Project QAE - 1,
O'ullivan, Assistant Project Field Engineer -
Ott, Lead Welding QCE -
Schrader, Project Field QCE Spielhagen, Project Field Engineer -
Stout, Assistant Project Field QCE -
Turnbow, Field Construction Manager -
NISCO T.
M.
Kopac, Site Manager Scp'ko, Site Engineer
General Electric Com an~
Nuclear Ener Division NED E. A. Gustafson, Site Manager T.
M. LeVasseur, gC Representative C. Roof, Mechanical Engineer General Electric Com an
- Installation and Service En ineerin IPSE
- Reactor Internals F. Forsythe, Site Manager D. Hess, gC Engineer J. Taylor, gC Engineer Peabod Testin Comoan M. llhalen, NDE Supervisor Notes 1 - denotes those present at exit interview, December 8, 1978 2 - denotes those present at exit interview, December 15, 1978 3 - denotes those present at exit interview, December 21, 1978 The inspector also interviewed other PPSL employees as well as employees of Bechtel, Peabody Testing Company, NISCO, and General Electric Company.
2.
Plant'Tour - Units
and
The inspector observed work activities in progress, completed work and plant status in several areas of the plant during general in-spection of the plant.
The inspector examined work for any obvious defects or noncompliance with regulatory requirements or license conditions.
Particular note was taken of presence of quality control inspectors and quality 'control evidence such as inspection records, material identification, nonconforming material identification, housekeeping and equipment preservation.
The inspector interviewed craft personnel, supervision and quality inspection personnel as such personnel were available in the work areas.
No items of noncompliance were identifie.
Licensee Action on Previous Ins ection Findin s
(Closed)
Followup Items (388/78-13-01):
Review of NCR 2969 and Equipment Maintenance Requirements and Records (EMRR) Form for Unit 2 Internals.
The inspector reviewed the EMRR's for the Unit 2 steam dryer and the shroud head and separator.
These documents had been revised to reflect the actual storage location of the components.
NCR 2969 regarding the storage of the internals has been dispositioned and corrective actions completed.
The inspector had no further questions on this matter.
4.
Reactor Coolant Pressure Boundar and Safet Related Pipin lrleTdin The following listed activities were examined and verified that they were being performed in accordance with the ASME Section III and IX Codes, PSAR Appendix D, the Bechtel guality Assurance Manual Section III, Site Specification M 204, M 207, drawings M-198 and M-199, and GE Specifications 22A4628.
filiCh
-
U I/elding of:
VRR-B31-1-FMA2 VRR-B31-2-RIB12 (Spacer Blocks)
DBB-119-1-FW2 HBC-13-1-FH1 The inspector verified selected detailed drawings, welding procedure, base and filler material as specified, welder qualification, quality control documentation, weld appearance, welding 'variables such as gas flow and amperage, and nonde-structive testing activities as appropriate.
No items of noncompliance were identified.
b.
Nondestructive Testin
- Unit
and Common Liquid Penetrant Testing of lleld 'Joint Nos:
SP-DCA-124-2, Weld Nos.
1, 2, 5, 7, 8, 'and ll DCA-110-2-FW3 SP-DBB-114-4, Meld No.
SP-GBB-106-2, lrleld No.
The inspector verified, as appropriate, surface preparation, qualification of examiners, and testing technique.
No items of noncompliance were identifie.
Reactor Coolant Pressure Boundar and Safet Related Pi in a.
Pi in S stem Work in Pro ress The inspector examined work activities for the Recirculation System Loop 8 and the Class II Control Rod drive insert/withdraw piping.
The inspector verified that the activities examined were in accordance with the ASME Code Section III, PSAR Appendix D, FSAR Sections 5.4.9 and 4.6.1, the Bechtel guality Assurance Manual Section III, GE Specification 22A 4628, Bechtel Specification M-164, M-204, and drawings YRR-B31-2, M-143, M-164-142(1)-3 and M-164-142(2)-3, the NISCO Field gA Manual and NISCO QC procedures.
The inspector observed handling, installation, protection, initial alignment, and identification.
The inspector reviewed associated gC inspection records, verified material certifi-cations, and reviewed gC Engineering certification records.
b.
Pi in S stem Installation Verification The inspector examined two partially completed piping runs and verified'that they were installed in accordance with approved drawings and specifications.
Piping runs examined were:
(1)
Main Steam Line C - Class I Portion.
The inspector verified conformance to FSAR Sections 5.2.3 and 5.4.9 and drawings VNB-821-1 and M-141.
(2)
HPCI Pump Discharge Line to the Feedwater System.
The inspector verified conformance to FSAR Section 6.3.2.2.1 and drawings EB8-102-1, DBB-119-1, DBB-120-1, DB8-120-2, M-155, and M-156.
No items of noncompliance were identifie.
Reactor Vessel Installation Units
and
The inspector examined protection of the installed reactor'vessels and stored closure heads for compliance with site procedures and PSAR Appendix 0 commitments.
The inspector reviewed the procedura1 requirements for vessel-protection and verified that required in-spections and preventive maintenance were being completed.
The inspector observed that openings were covered as required, work platforms inside the Unit 1 vessel were nonflammable and that Unit 1 vessel access was controlled.
Documentation reviewed by the inspector included:
Field Inspection Procedure G-5, Revision
Project Special Provisions Notice SF/PSP G-5.1, Revision
Equipment Maintenance Requirement and Record Form for Units
and 2 Reactor Vessels and for Reactor Vessel Closure Heads No items of noncompliance were identified.
7.
Reactor Vessel Internals a
~
Protection of Stored Vessel Internals - Units
and
The inspector examined protection of the stored reactor vessel internals for compliance with site procedures and PSAR Appendix 0 commitments.
The inspector reviewed the procedural require-ments for internals protection and verified that required in-spections were being completed.
The inspector observed in-plant storage of the steam dryer and the shroud head and separator for Units 1 and 2.
Documentation reviewed by the inspector included:
Field Inspection Procedure G-5, Revision
Project Special Provisions Notice SF/PSP G-5.1, Revision
Equipment Maintenance Requirements and Record (EMRR) Form for Units 1 and 2 steam dryer and the shroud head and separator
Previously identified, item 388/78-13-01 regarding the storage of reactor internals was closed during this inspection.
No items of noncompliance were identified.
b.
Installation of Internals - Unit
The inspector examined work in progress relative to the in-stallation of incore housings and observed the liquid penetrant examination of the root weld for incore housing 56-33.
The inspector verified that the NDE was being accomplished in accordance with the documents listed below:
GE Specification 22A42B, Revision
GE I&SE Liquid Penetrant Procedure 18XA7400, Revision
Certification of NDE Examiner in accordance with the
- GE I&SE Nuclear Quality Assurance Manual Section 12.0 Incore Housing Installation Travelers 15T-54A and 15T-OA No items of noncompliance were identified.
8.
Fire Prevention/Protection The inspector examined fire prevention and protection activities including the review of site procedures and the observation of field activities in the area of fire prevention and protection.'he inspector observed the followi-ng in work areas:
Protective coverings are nonflammable Flammable materials such as gas cylinders stored in designated areas Combustible scrap materials and trash removed Flammable coating materials storage areas Metal nonflammable scaffolding inside the reactor vessel and other critical location Cutting and welding processes in accordance with site require-ments Temporary heating processes such as weld preheating in accordance with site requirements No smoking area restrictions observed Fire protection/prevention equipment provided and controlled The inspector examined the following documents relative to the above:
Project Fire Control and Emergency Plan - August 13, 1976 Bechtel Safe Practices Manual - July 17, 1974 Supervisor's Safety Meeting Notes - December 1,
1978 Bechtel Safety Manual - Section 5 - Undated Bechtel Fire Protection and Prevention Manual - Undated 9.
Containment Penetrations
- Unit 2 The inspector observed the installation of containment electrical penetration 2W106B and reviewed pertinent documents to verify that they were technically adequate, current and approved.
The inspector verified that the installation activities were being conducted in accordance with commitments in the PSAR Appendix D; FSAR Sections 3.1.2.5 and 3.8.1; Bechtel Specification E-135; Westinghouse Installation Instruction PEN-TR-76-19, revised July 7, 1978; and, gCI 6.6, Revision 5.
The inspector examined the following relative to the above:
Method of assembly consistent with design requirements Measures to protect installed components Installation including handling and bolting
gC inspection activities Installed penetration identification The inspector also reviewed the following documents relative to the above:
gCIRs E-135-2W1068-1 and E-135-2W1068-2 NCRs 3104 and 3237 These nonconformance reports document conditions identified by the licensee's quality assurance program regarding the installation of electrical penetrations.
No items of noncompliance were identified.
10.
Exit Interview At periodic intervals during the course of this inspection, meetings were held with facility management (dates and attendees are denoted in Detail 1) to discuss inspection scope and findings.