IR 05000454/1980019
| ML19345C634 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 10/29/1980 |
| From: | Clint Jones, Gerald Williams NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19345C628 | List: |
| References | |
| 50-454-80-19, 50-455-80-18, NUDOCS 8012080035 | |
| Download: ML19345C634 (5) | |
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'OL U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF_ INSPECTION AND ENFORCEMENT
REGION III
Reports No. 50-454/80-19; 50-455/80-18
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Docket Nos. 50-454; 50-455 Licenses No. CPPR-130; CPPR-131 Licensee: Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 j
Facility Name:
Byron Nuclear Generating Station, Units 1 and 2 Inspection At:
Byron' Construction Site, Byron, IL and Chicago, IL Inspection Conducted: September 10 - 12 and 30, 1980 S
arc u Inspector:
C. E." Jones
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M Approved By:
.C.WilliN, Chief fB/Ef/T4.
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Projects Section 2
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Inspection Summary Inspection on September 10-12, and 30, 1980 (Reports No. 50-454/80-19; 50-455/80-18)
Areas Inspected: Status of previous identified unresoh ed items; status of action, resolution and documentation of items reported in compliance with requirements of 10 CFR 50.55(e). This inspection involved a total of 27 inspector hours on site by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
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Principal Licensee Employees The inspection was performed at the construction site and the corporate office in Chicago, Illinois. Those persons contacted at the Byron site were as follows!
- G. Sorenson, Project Superintendent
- J.
Mihovilovich, Lead Structural Engineer
- R. Tuetken, Lead Mechanical Engineer
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- J.
T. Porter, Senior QA Inspector
- J.
T. McIntire, QA Supervisor J. T. Westemeier, Project Engineer J. Kaminski, QA Engineer R. Choinard, QA Engineer Blount Brothers V. Williams The inspector also contacted and interviewed other licensee and contractor personnel including supervisors and traftsme'n.
Licensee Employees Contacted At Corporate Office - Chicago, Illinois on September 30, 1980
- J. Westermier, Project Engineer
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- L. Bowen, Licensing Engineer i
- Denctes those present at the respective exit interviews.
Licensee Action on Previous Inspection Findings (0 pen) Unresolved Item (50-454/80-14-01) Trash observed in the annulus between Unit 1 biological shield and reactor pressure vessel insulation.
Although the debris was scattered in the annulus, it was previously concen-trated in the south-west quadrant. A tour of the area during the present inspection indicated that all of the foreign material had not been removed.
This item' remains unresolved.
(Closed) Unresolved Item (455/80-13-02) Storage of Unit 2 Reactor Pressure Vessel head. The pigeons had been removed and their access to the building blocked. The bird droppings had been cleaned from the lower section of
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the head and a fresh protective coating had been applied to the lower' head and stud holes. -In addition, the head has been completely covered with a protective sheet of plastic. This item is resolved.
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Functional or Program Areas Inspected The inspector reviewed the status of items previously reported by the licensee in compliance with requirements of 10 CFR 50.55(e) and 10 CFR Part 21.
Several of the items reviewed have been open for one or two years and will remain open pending review of test data from the pre-operational test program.
Other items have been analyzed, corrected, inspected, and approved.
These items have been identified as closed.
1.
Velan Globe Valves During the review of Velan supplied valves in response to a March 30, 1979 letter from J. G. Keppler to Byron Lee, Jr. transmitting IE Bulletin No. 79-04, approximately 60 globe valves per station were identified as having incorrect weights when compared to the drawings.
Correct weights for the valves have been determined by recalculation and/or actual weighing by Velan Valve Corporation and the affected drawings hive been corrected and redistributed.
The seismic Category I systems which have been affected by the incorrect weights are as follows:
a.
Chemical and Volume Control System (CV)
b.
Safety Injection System (SI)
c.
Essential Service Water System (SX)
d.
Chilled Water System (WO)
Auxiliary Feed Water System (AF)
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A final check process using the final equipment and installation data is scheduled to be performed on all seismic Category I systems prior to fuel load. Any modifications that are required due to incorrect i
valve weights will be made at that time. The PRPSYS computer code, which is described in Appendix D.8 of the Byron /Braidwood FSAR, will be used to perform the check. This item will be transferred to Opera-tions since these tests will be included as part of the pre-operational test program.
2.
Corrective Action Regarding Welding of Cable Trays and Supports, Reported per 10 CFR 50.55(e)
This item was previously resolved by an NRC inspector in IE Inspection Reports No. 50-454/78-06 and No. 50-455/78-06.
3.
Defective Integrated Circuit Chips for Process Control Systems (Reference 10_CFR 50.55(e) Report, January 19, 1978)
Two RIII inrpectors reviewed the corrective action taken, which included the issuance of Nonconformance Report (NCR) No. F-163 and attachment.=.
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This action placed the process control system cabinets in hold until the integrated circuit chips (Ratheon RC 747D) could be replaced. The in-spector marked this item closed (IE Reports No. 50-454/78-01; 50-455/78-01; 50-454/79-17; 50-455/79-17) based on the documentation reviewed. At present construction is placing this item in open status until the various circuits have been tested prior to startup.
4.
Rod Drop Ahalysis, Reported per 10 CFR 50.55(e)
This item was considered by the licensee to be applicable to Byron and Braidwood Stations and was a 10 CFR 55(e) reportable item. Con-sidering the time span prior to startup, the licensee does not intend to take action prior to the issuance of a Westinghouse Topical Report containing long term solutions. Based on the status of the plant construction, this item is being transferred to Operations for followup.
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5.
Post Tensioning Buttonhead Cracks - Reported per 10 CFR 50.55(e)
Closed by a RIII inspector in IE Reports No. 50-454/79-01; 50-455/79-01.
Report of inspection December 11-12, 1979.
6.
Buttonhead Deficiency, Reported by 10 CFR 50.55(e)
Several meetings have been held concerning this item.
Inryco and their. consultants have performed several tests cf the material, heat treatment, etc. and have analyzed the test data. Documentation of the test and test data have been reviewed by NRC personnel.
Installa-tion of the tendons is in progress in Byron Unit 1.
This iten remains open pending additional document review and observation of the tendon installation.
7.
Undetectable Failures in ESEAS, Reported by 10 CFR 50.55(e)
The licensee stated this item would not be reported until fuel loading was initiated.
Based on this timing, the item remains open and will be transferred to Operations.
8.
Heating, Ventilating, and Air Conditioning (HVAC) Deficiencies, Reported
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per 10 CFR 50.55(e)
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These deficiencies and the proposed corrective action were reviewed by a RIII inspector and documented as closed in IE Reports No. 50-454/79-01; 50-455/79-01.
9.
Limitorque-Valve Actuators, Reported per 10 CFR 21
'the inspector reviewed the certificate of compliance and determined that these' were actually certificates of conformance.
This item is considered closed. The inspectors report is documented in IE Reports No. 50-454/79-17; 50-455/79-17.
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10.
Unacceptable Linear Indications in Weldments of Byron U-1 Steam
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Generator Lower Lateral Support Frame - per 10 CFR 50.55(e)
The original design specified a single support welded to the desired configuration. The large weldments in the heavy structural steel caused cracking in the welds. The support was re-designed to require-bolted connections. The inspector observed the' bolted units in place in the field. The designed support was. checked against drawings 22281 Revision F, sheet 3; 22281 Revision D, sheet 5 and 22281 Revision G sheet I and observed-to be as specified. This item is considered ~ closed.
for Units 1 and 2 at Byron.
Exit Interview The inspector met with licensee representatives (denoted under Persons Contacted) at the. conclusion of the' inspection on September 12 and 30, 1980. The inspector summarized the purpose and findings of the inspection.
The licensee acknowledged the findings reported herein.
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