IR 05000387/1979032
| ML17138B070 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/15/1979 |
| From: | Ebneter S, Paolino R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17138B066 | List: |
| References | |
| 50-387-79-32, 50-388-79-17, NUDOCS 8002140425 | |
| Download: ML17138B070 (7) | |
Text
U.S.
NUCLEAR REGULATORY.COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT 50-387/79-32 epprt No 50-388/79-17 Oocket'o 50 387/50 388 Region I ense No CPPR-101, CPPR-102 priority Pennsylvania Power and Light Company 2 North Ninth Street Category Allentown, Pennsylvania 18101 Susquehanna Steam Electric Station, Unit Nos.
and
Investigation at:
Berwick, Pa.
Investigation conduct d
October 1-5, 1979 Investigators:
R.
. Paolino, Reactor Inspector date signed date signed date signed, Approved by:
neter, C ref, Engsneering Support Section b2, RC&ES Branch date signed-rr is-i'vC date s'ign d
Investi ation Summar
Combined Ins ection of Units
and 2 on October 1-5 1979 Re ort No. 50-387/79-32 Areas Ins ected:
Routine, unannounced inspection by regional based inspector of work performance, partially complete work and completed work for select process'ariables associated with reactor protection systems, engineered safety features actuation system and normal plant control systems.
The inspection also includes the review of pertinent work records and quality records for instrument components selected.
The inspection involved 35 inspector-hours onsite by one regional based.s>
inspector.
Results:
Of the two areas inspected, one apparent item of noncompliance was identified in the area of work performance (Infraction - failure to follow instru-
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nt procedures/instructions
- Paragraph 3.B).
Region
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Form 143 (Rev. October 1977)
g 00P140
DETAILS Persons Contacted Penns lvania Power and Li ht Com an H. Block, Senior Project Engineer
."J. Green, Resident NOAE T. Oldenhage, Resident Engineer J.
Rizzo, Cost Schedule Engineer R. Prego, Site gAE Bechtel Cor oration C. Cranston, Resident Mechanical Engineer J. Dahnert, Lead Receiving gC D. Davis, Instrument Engineer M. Davis, General Foreman
"P. Drucker, Assistant Lead gAE P. Ericksen, Mechanical Engineer L. Hedrick, Instrument Engineer P. Kessler, Receiving gC
"H. Lil'ligh, Project gAE S. Hurray, Lead Instrument Engineer D. Oschal, Instrument HVAC Engineer R.
Rezak, Area Lead Instrument Engineer
"K. Stout, Area Project F(CE E. Strzelecki, gC Lead Instrument Engineer J. Tutini, Lead Small Pipe and Instrument Supervisor D. Yensan, Lead Small Pipe Engineer J. Maddington, gC Electrical Engineer NRC Resident Ins ector
"R. Gallo
" Denotes personnel present at exit interview.
Plant Tour (Units 1 and 2)
The inspector observed work activities in progress, completed work and plant status in several areas of the plant during general inspection of the facility.
The inspector performed visual inspection of installed instrument components, wiring and conduits for obvious defects, deviations or nonconformance with established procedures, licensee commitments and regulatory requirements.
No items of noncompliance were identifie.
Instrumentation Com onents/S stem - Work Activities Units 1 and 2.
The inspector examined work performance, partially completed work and completed work pertaining to select process variables associated with the Reactor Protection System, Engineered Safety Features Actuation System and Normal Plant Control System.
The inspector verified that the requirements of applicable specifications, work procedures, test procedures and inspection procedures are being accomplished in accord-ance with SAR commitments and NRC requirements in areas relating to identification, type, range, installation and inspection with the exception of item noted in paragraph B.
A.
Items examined for this determination include:
Battery Room Exhaust Air Control System Components FT-08612B, FE-08612B and TV-08612B.
Purchase Order Specification J-3A and J-03A.
P8ID Drawing VC-178 sh 1 and 2.
Installation Drawings JD-12-10-1 rev. 2, JD-12-10-lA rev.
3, and JD-12-10-1B.
Emergency chilled water components TV-08612B, PP-08612B1, PI-08612B1, PI-08612B2, TI-08612B1, PP-08612B2, TE-08612B, TI-08612B2 and HV-08613B.
Location Drawing VC-12-10 and VC-12-11.
Emergency condenser water circulation pump instrument components TI-08612A2, TE"08612A, PP-08612A, PI-08612A1, TIC-08612A, TV-08612A, TT"08612A, FY"08612A, PI"08612A, FT"08612A, FI-08612A and FE-08612A.
PAID Drawing 8856-M-186.
Procedure Numbers FP-J-1, FP-J-2, FP-J-3, FP-J-4, FP-G"11.
Specification Numbers 8856-M-204, 8856-M-167, 8856-M-364, 8856-G-
and 8856-JG-16.
Support Fabrication Mork Order Numbers 4J-22, 4J-28, 4J-55 and 4J"65.
No items of noncompliance were identifie B.
The inspector examined eight seismic instrument support wall mounted installations using the rigid wall bracket configuration illustrated on drawing J-G1014-9, Revision 3.
The inspector noted that in two of the installations, the instrument support bracket for flow transmi'tter FT-08612B, elevation 783'- - 0", area 12 and level transmitter LT"15776B, elevation 645'0", area 25 did not conform to specification mounting requirements of specification C-72, Revision 4, paragraph 4.1.6, which states,
"For concrete structures. the minimum distance between expansion anchor centerlines shall be 10 nominal bolt diameters unless otherwise specified by the project manager."
Drawing J-G1014-9, Revis,ion 3, requires 5/8 inch diameter holes (minimum) for < inch fasteners (minimum).
Based on criteria for specification C-72 (noted above)
expansion anchor centerlines should measure 5 inches.
The expansion anchor centerlines for the two instrument mounts referenced above measured 3 - 3/4 inches.
The licensee was informed that this was an item of noncompliance and an infraction of 10 CFR 50, Appendix B, Criteria V, which states,
"Activities affecting quality shall be prescribed by documented instructions....and shall be accomplished in accordance with these instructions...."
(79-32-01)
Instrument Com onents/S stem -
ualit Records Units
and 2.
The inspector reviewed pertinent work and quality records for instrument components used to monitor process variables associated with the Reactor Protection System, Engineered Safety Features Actuation Systems and Normal Plant Control System.
The inspector verified that the records meet established procedures and that the records reflect work accomplishment consistent with NRC requirements and SAR commitments in the areas of receipt inspection, material qualifications, Installation Inspections, and control of nonconforming items.
Documents examined for this determination include:
gCI-SM-1.03 rev. 3, HVAC and air condition installations subcontract surveillance.
gCI-J"l. 10 rev. 4, Installation of Instruments.
gCI-P-l. 10 rev. 7, Piping Subassembly Fabrication, Installation and Rework.
gCI-P-1.00 rev. 2, Piping Completed Line Installatio QCI-SM-1.05 rev.
0, Installation of HVAC Instruments and Control s Subcontract Survei 1 1 ance.
Surveillance Record Numbers QCIR"JIM-186 log JIR-241, QCIR-JIM-186 log JIR"378, QCIR-JIM-186 log JIR-390, QCIR-JIM-186 log JIR"391, QCIR-JIM"186 log JIR-356, QCIR"JIM-186 log JIR-312, QCIR-JIM"186 log JIR-252 and QCIR-CIM-186 log CIR-8249.
Field Change Notices 757, 792.
No items of noncompliance were identfied.
5.
Exit Interview The inspector met with licensee and construction representatives (denoted in Details paragraph 1) at the conclusion of the inspection on Gctober 5, 1979.
The inspector concluded the inspection with a summarization of the purpose and scope of the inspection and concurrence by the licensee of the inspection findings.