IR 05000387/1978022
| ML17138A506 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 01/08/1979 |
| From: | Ebneter S, Jernigan E, Walton G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17138A505 | List: |
| References | |
| 50-387-78-22, NUDOCS 7902230202 | |
| Download: ML17138A506 (8) | |
Text
Report No.
78-22 U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Docket No.
50-387 License No.
CPPR-101 Priority Category Licensee:
Facility Name:
Sus uehanna t am Electr'nspection at:
Berwick, Pennsylvania
~
InsPection conducted:
December 12 14, 1978 Inspectors:
G. Walton, Reactor Inspector
~q/
E. Jernigan, Reactor Inspector ion, Unit
date signed-iI-~F date signed date signed Approved by:
S.
D. Ebneter, Acting Chief, Enginee'ring Support Section No. 1, RC8ES Branch da e signed Ins ection Summar:
Ins ection on December 12-14, 1978 Re ort No. 50-387 78-22
~AI:
R f, db d
f by df bb df d
f component storage, installation of incore housings, in reactor pressure vessel, welding of safety-related piping and preservice inspection activities.
The inspection involved 46 inspector-hours onsite by two NRC inspectors.
Results:
No items of noncompliance or deviations were identified.
~
Region I Form 12 (Rev. April 77)
e%(~ %('l f % yfN)
l "..s ',.e,>'l."~,w >
DETAILS Persons Contacted Penns 1 vania Power and Li ht Com an L. Ballard, Site QA Engineer
- R. Beckley, Site QA Engineer
- S. Denson, Assistant Project Construction. Manager E. Carroll, Site QA Engineer
- J. Green, Resident Nuclear QA Engineer
- A. Male, Assistant Manager Nuclear Plant Engineering
- T. Oldenhage, Resident Engineer
- R. Shovlin, Assistant Project Director United States Nuclear Re ulator Commission
- R. Gallo, Resident Reactor Inspector Bechtel Cor oration
Oman, Lead Storage and Maintenance Engineer K. Kutner, Warehouse Supervisor
- K. Stout, Assistant Project Field QC Engineer A. Kenjura, Site QA Engineer T. Seymour, Site QA Engineer L. Price, Engineer
- C. Turnbow, F.
C.
M.
- J. O'ullivan, Assistant P.
F.
E.
- A. Spielhagen, P.
F.
E.
- M. Boone, L.
F.
W.
E.
General Electric Com an F. Forsythe, I8SE Reactor Internals Site Manager D. Hess, Site QA Supervisor
denotes those present at the exit interview
.3 2.
Plant Tour The inspectors observed work activities in progress, completed work, and plant status in several areas of the plant during a
plant status inspection of the plant.
The inspectors examined work items for any obvious defects or noncompliance with regulatory requirements.
Where more detailed inspection of an area was con-ducted, the inspection scope and findings are described in other paragraphs of the report.
3.
Reactor Coolant Pressure Boundar Pi in Weldin The following listed activities were examined and verified that they were being performed in accordance with ASME Section III and IX Codes, PSAR Appendix D and the Bechtel guality Assurance Manual.
Recirculate Line VRR-B31-1 FW-A1, Mtl. SA 240 Type 304 to SA 336 F8 The inspector verified weld card, welding procedure P8-AT-AG-R2, welder qualifications (PlAl, P6A9, PZ5 and P7K), quality control documentation, weld appearance, welding variables, and non-destructive testing activities as appropriate.
'o items of noncompliance were identified.
4.
Reactor Vessel In-Core Housin Installation The following listed activities were examined for the installation of in-core housings in the reactor pressure vessel.
a ~
b.
C.
d.
Observation of welding Welder qualification Liquid penetrant examination results Review of process controls, hold points and calibration of measuring equipment No items of noncompliance were identifie.
Licensee Action on Previous Ins ection Findin s (Open)
Unresolved Item (387/78-16-03):
The inspector requested final examination and evaluation results relative to the volumetric examination of'he dissimilar metal welds in the recirculation nozzles..
Cognizant licensee personnel, indicated that the final examination report had not been issued, but would be available on January 16, 1979.
The inspector's audit of examination data available during the inspection included radiographic data of the N2J nozzle safe-end to extension piece weld.
The radiographic interpretation sheet for this nozzle indicated that the level III film interpreter had rejected this weld.
The inspector also ob-served piping being fit-up to the recirculation nozzles in ques-tion.
The licensee representatives stated that the evaluation was ongoing and their position would be determined by the results.
This item remains unresolved.
6.
Safet -Related Com onents Observation of Work and Work Activities The inspector audited procedures to control the storage, handling and, protection of those pressure retaining components which will become part of the reactor pressure boundary.
The inspector also observed the= implementation of portions of these procedures and reviewed associated records.
These audits and observations were made to determine if the esta-blished program and its implementation were consistent with the requirements of Appendix D of the Facility PSAR.
a.
Stora e, Handlin and Protection The inspector toured safety-related equipment storage areas which included:
1) the on-site warehouse; 2) Pittston Ware-house; 3) plant drywell; and, 4) reactor building.
The tour was conducted to determine whether storage requirements were being met relative to:
1) protection; 2) identification; 3)
identification of nonconforming conditions; 4) lubrication; 5)
preservative/heaters; and, 6) maintenance/surveillance activities.
The inspector observed the storage warehouse to be weather-tight, heated enclosures constructed of steel with concrete
.
floors which contain an automatic sprinkler fire suppression
system.
The storage environment and protection afforded by these warehouses met or exceeded the equipment supplier's requirements.
Additionally, the inspector observed the storage/protection provided for the recirculation system pumps and isolation valves, main steam isolation valves, residual heat removal pumps, core spray pumps and core spray pump barrels.
The inspectors found that the storage/protection provided the above equipment to be consistent with the requirements of the applicable procedures/specifications, except for the core spray pump barrels.
These barrels were stored in-place and were filled with water.
This condition was identified by the licensee during this inspection.
Corrective action to preclude and mitigate this storage problem were in progress.
The inspector stated these actions by the licensee's storage contractor were responsive to the conditions observed.
The inspector had no further questions regarding this item at this time.
No items of noncompliance were identified by the inspector.
b.
Work Procedures/S ecifications The inspector examined installation drawings and specifica-tions associated with the recirculation pumps.
These pumps were installed in position on elevation 704'f the reactor building.
The manufacturer's installation specification IE-3429-6 and the contractor's drawing M-242, Revision 10 were reviewed.
The inspector determined these documents to be applicable for this equipment.
Additionally, the inspector audited inspection records associated with pump volute installa-tion.
This review indicated that the installation was performed in accordance with the appropriate drawings and specification.
No items of noncompliance were identified by the inspector.
7.
Unresolved Item Unresolved items are matters about which more information is required in order to ascertain whether they are, acceptable items, 'ftems of non-compliance or deviations.
An unresolved item disclosed during a pre-vious inspection and reviewed during this inspection is discussed in Paragr aph 5.
~
~
~
~
~
~
~
~
~
~
~
~
~
~
8.
Exit Interview The inspector met with the licensee representativies (denoted in paragraph 1) at'the conclusion of the inspection.
The inspectors summarized the purpose and scope of the inspection.