IR 05000454/1980014
| ML19337A529 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 08/18/1980 |
| From: | Erb C, Clint Jones, Williams C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19337A528 | List: |
| References | |
| 50-454-80-14, 50-455-80-13, NUDOCS 8009290193 | |
| Download: ML19337A529 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Reports No. 50-454/80-14; 50-455/80-13 Licenses No. CPPR-130; CPPR-131 Docket Nos. 50-454; 50-455 Licensee: Commonwealth Edison Company P.O. Box 767 Chicago, IL 60690 Facility Name: Byron Nuclear Generating Station, Units 1 and 2 Inspection At: Byron Site, Byron, Illinois Inspection Conducted: July 28-29, 1980 C,
W if - /.6~- 74 Inspectors:
C. E. Jones a f0 C.
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Approved By:
C. C. Williams, Chief Projects Section 2 Inspection Summary
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Inspection on July 28-29, 1980 (Report No. 50-454/80-14; 50-455/80-13)
Licensee audits relative to installation of the NSSS Areas Inspected:
records of the setting and alignment of the Unit I reactor pressure System; vessel (RPV); records of the Unit I and Unit 2 RPV internals and storage of the Unit 2 RPV head. Observed Unit I cavity liner and installation of the in-core flux tubes. Observed welds previously rejected by the Testing Laboratory on instrument cabinets manufactured by Westinghouse and Systems This inspection involved a total of 26 inspector-hours on site i
Control.
by two NRC inspectors.
No items of noncompliance or deviations were noted.
Results:
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DETAILS Persons Contacted Principal Licensee Employees
- G. Sorensen, Project Superintendent
- J. T. McIntire, QA Supervisor
- J. T. Porter, Senior QA Inspector
- J. De Rosia, Field Engineer, Station Construction
- R. Tuetken, Lead Field Engineer R. R. Guse, Field Engineer Nuclear Installation Services Company R. Larkin, QA Manager Hunter Corporation R. Wilhelm, QC Inspector The inspectors also contacted and interviewed other licensee and contractor pe sonnel including supervisors and craftsmen.
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- Denotes those present at the exit interview.
Licensee Action on Previous Inspection Findings River Screen (0 pen) Unresolved Item (50-454/80-12-03; 50-455/80-11-03):
House Essential Service Water make-up pump diesel foundation anchor bolts.
The bent anchor bolts for the Unit 2 diesel foundation anchor plate hadThe been removed and replaced with straight bolts meeting specifications.
licensee had removed the grout supporting the Unit I diesel foundation anchor plate, inspected the anchor bolts and replaced those that were bsnt.
The inspectors observed the bolts under both base plates to be straight and concurred with the licensee that grouting of the diesel foudnations could proceed.
The following day the Project Superintendent was contacted by telephone and informed that the subject of the unresolved item should remain open pending additional discussions.
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Section 1 Prepared by C. E. Jones Reviewed by C. C. Williams, Chief Projects Section 2 1.
Site Tour The inspector made a tour of various safety related sections of the plant accompanied by the QA Supervisor. Many of the areas concerning previous inspection findings were observed and potential resolutions discussed. Details of significant items noted during the tour are recorded in other sections of the report.
2.
Construction Status Discussions concerning the status of construction are summarized below.
Installation of the Unit I reactor coolant loop is complete.
a.
Other Unit 1 Class 1 installation work, including some revisions, remain to be done.
Installation of the Unit 2 reactor coolant loop is approximately b.
80 Jer cent corplete.
Completion of cold hydrostatic test of Unit I reactor pressure c.
vessel is estiwated for June 1, 1981.
Initiation of containment structural integrity test is estimated d.
for April 1981.
3.
Record Review for RC Loop Accumulators The available records, a Westinghouse Quality Release (QR) and Code Form N-1A, Manufacturers Data Report for Nuclear Vessels, were reviewed for each of the four Unit 1 accumulators. The QR summary of the documentation on file met specification and regulatory requirements.
A summary of the equipment documentation reviewed is as follows:
Four (4) accumulators fabricated by Southwest Fabrication and a.
Welding, Houston, Texas, were identified by the NSS System Supplier as follows:
CAE SI ATAT-01 CAE SI ATAT-01 CAE S1 ATAT-03 CAE S1 ATAT-04 P.O. Comm. twealth Edison Co. 130531 P.O. NSSS 215203 W Quality Release (QR)
21911-3-
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Vessel No.
National Board No.
Year Built 1976 0009 299 0008 298 1976 1976 0010 300 1976 0012 302 Applicable ASME Code: Section III, Edition 1974, 1974 Summer Addenda, Case No. - Class 2 3.
Reactor Cavity The inspector observed the Unit I reactor cavity and the access tunnel provided for the in-core instrumentation at approximate elevation between 353' and 346'.
Although work was not in progress at the time of our entry, additional work remained to be done on the in-core instrumentation.
Since work was not in progress and the area was a sump, safety and Quality Control personnel from Hunter Corp. refused personnel access to the area until the quality of the air was verified adequate for j
The air was checked for exygen content and then a portable breathing.
blower was installed to assure adequate air movement. This was an
excellent example of effective safety.
A considerable amount of debris was observed on the floor under the incore flux tubes. Also trash was observed in the narrow space between the biological shield concrete and the preformed insulation covering the reactor pressure vessel. The major portion of thisThe debris was observed in the South-West quadrant of the cavity.
licensee initiated a clean-up of the area within approximately two hours from the time it was observed. This is an unresolved item.
(454/80-14-01)
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Section II Prepared by C. M. Erb Reviewed by D. H. Danielson, Chief Engineering Support Section 2 1.
Setting of Reactor Pressure Vessels-Units 1 and 2 Reliance Truck transported and lifted the reactor vessels for setting and NISCO performed the leveling and setting operation.
Both vessels for Unit 1 and 2 were set to Procedure RV-3004-1-A with reference material (1) S&L S1115, Revision K (2) W drawing 1142E17 (3) W setting procedure (4) B&W RV Service Manual.
Sign offs by engineering and QA had been properly made. Measuring instruments used at various steps in the procedure were referenced by serial No.
and could be traced to calibration from an NBS master instrument.
Both reactor vessels were manufactured by B&W se the process steps
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were identical.
ASME,Section III, 1977 Edition, without amendment was used generally as requirements for NSS components, although in some cases the date of contract for the item governed.
No items of noncompliance or deviations were identified.
2.
Control Rod Drive Mechanism Welding Units 1 and 2 The seal welding has been completed on both reactor vessel heads by NISCO. The procedures used and approved by CECO in an audit for the Unit I closure head are as follows:
SWPS-132-1, Revision B, Weld Procedure SWPS-132-2, Revision C, Weld Repair Procedure CRDM-3004-1-A, Revision C WPS 80.2, Revision F, Weld Procedure Specification CRDM 3004-2-A, Revision A, Hydrotest During 1978 u
'979, CECO conducted 12 audits on t; e various areas of NISCO respo.u ility for CRDM installation. These audits covered storage, qualification of welds and QC personnel, nonconformances, corrective action, and receiving inspection.
No items of noncompliance or deviations were identified.
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3.
Internals Installation - Unit 1 Audit No. BY-MS-1 was made by the Pittsburg Testing Laboratory on internals work by NISCO. Three people were found qualified a.
to Bolting Procedure ES-149. Torque wrench S/N 751 223 was calibrated on December 18, 1978, by PTL. Bolts 3/4" diameter
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were torqued to 230 foot pounds.
Audit No. 1749 by CECO was made on welding of the fuel transfer b.
tube.
Control of materiels was maintained and the weld was made as follows:
Weld Procedure Spec. Size Material Filler Welder Root
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80.1 20"x3/8" Stainless ER 308L 0631 Open Butt No items of noncompliance or deviations were identified.
4.
Storage of Unit 2, Reactor Vessel Head An inspection of the reactor vessel head revealed that pigeons had invaded the storage building and droppings were on the top flange and While the interior of the holes in the flange was in the stud holes.
protected by some coating, there was evidence that some corrosion This situation is unacceptable and will require might be taking place.
some clean-up and re-coating and then either covering the exposed areas or ousting the birds. This is an unresolved item.
(455/80-13-02)
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, Unresolved items disclosed during the inspection are dis-or deviations.
cussed in Paragraph 3,Section I and Paragraph 4,Section II.
Exit Interview
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The inspectors met with the licensee representatives (denoted under Persons Contacted) at the conclusion of the inspection on July 29, 1980. The The inspectors summarized the purpose and the findings of the inspection.
licensee acknowledged the findings reported herein.
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