IR 05000259/1986019
| ML18031A550 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/19/1986 |
| From: | Blake J, Liu W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18031A549 | List: |
| References | |
| 50-259-86-19, 50-260-86-19, 50-296-86-19, IEB-79-02, IEB-79-14, IEB-79-2, NUDOCS 8607100365 | |
| Download: ML18031A550 (8) | |
Text
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UNITEO STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323 Report Nos.:
50-259/86-19, 50-260/86-19, and 50-296/86-19 Licensee:
Tennessee Valley Authority 6N38 A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Docket Nos.:
50-259, 50-260 and 50-296 License Nos.:
DPR-33, DPR-52, and DPR-68 Facility Name:
Browns Ferry Inspection Conducted:
May 27-30, 1986 Inspector:
~
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W.
C. Li Approv d by:
J.
J
~ Blak, S ction Chief Engineering Branch Division of Reactor Safety Date Signed Date Signed SUMMARY Scope:
This routine, announced inspection involved previously opened items in the areas of seismic analysis for as-built safety-related piping systems (IEB 79-14), pipe support baseplate designs using concrete expansion anchor bolts ( IEB 79-02),
and safety-related cable tray support systems.
Results:
No violations or deviations were identified.
8607100365 860626 PDR ADOCK 05000259
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
"J. Swindell, Superintendent, Operations/Engineering
- T. Ziegler, Maintenance Superintendent
- D. Nye, Project Management
"W. Smathers, Lead Engineer, CEB
"B. Morris, Compliance
"R. Schulz, Compliance
"J. Savage, Compliance
- W. James, Project Management Other licensee employees contacted included engineers, technicians, security office members and office personnel.
NRC Resident Inspectors
"G. Paulk, Senior Resident Inspector
- C. Patterson, Resident Inspector
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on May 30, 1986, with those persons indicated in paragraph above.
The inspector described the areas inspected and discussed in detail the inspection findings listed below.
No dissenting comments were received from the licensee.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.
3.
Licensee Action On Previous Enforcement Matters a
~
(Closed) Violation 296/86-02-02, Inadequate Corrective Action for RBCCW Support H17A.
TVA's letter of response, dated April 17, 1986, has been reviewed-and determined to be acceptable by Region II.
The inspector held discussions, with licensee's representatives and examined the corrective actions as stated in the letter of response.
The inspector concluded., that TVA had determined the full extent of the subject violation, performed the necessary survey and followup-actions to correct the present conditions and develop the necessary corrective actions to preclude recurrence of similar circumstances.
The corrective actions identified in the letter of response have been implemente b.
C.
(Closed)
Unresolved Item 259, 260, 296/85-26-04, Acceptance Criteria for Pipe Support Inspections.
This item involved Browns Ferry Instruction MAI-23 which was used by the gC inspectors to perform inspections for safety-related pipe supports.
This instruction required full-thread engagement for threaded connections.
Further, the instruction did not specify that the gC inspectors were required to verify torque values when bolts were used for connecting the snubber housing and the transition tube/forward bracket.
Results of the field inspection revealed that many of the lock nuts had a lack of thread engagement, and bolts used for connecting snubber housing and the transition tubes were not torqued to the specified values as required by the manufacturer's instructions.
The inspector held discussions with licensee's representatives regarding the aforementioned concerns and reviewed related documents.
It was found that TVA had revised
'nstruction MAI-23 to include the acceptance criteria with respect to bolt thread engagement and the torque requirements for support inspections.
This item is closed.
(Closed)
Unresolved Item 260/85-26-03, Interim Acceptability of Plant Operation for IE Bulletin 79-02 Requirements.
This item involved the IE Bulletin 79-02 program with regard to the evaluation of pipe supports and anchor bolts for which the minimum factor of safety had to be met to assure safe operation of the plant.
The inspector held discussions with licensee's representatives regarding the above concerns and reviewed related documents.
It was found that inspections for Unit
in regard to IE Bulletin 79-02 are scheduled to be completed by July ll, 1986.
The inspections performed are to assure that the minimum factor of safety is met otherwise a failure analysis must be performed to ensure that the system still can serve its intended function.
This item is closed.
d.
(Open)
Violation 260, 296/86-02-01, Inadequate Design Controls for Safety-Related Piping Systems.
TVA's letter of response, dated April 17, 1986, has been reviewed by Region II.
The inspector held discussions with licensee's representatives regarding the corrective actions to be taken by the licensee.
It was agreed that TVA would provide Region II with a supplemental response in the near future to address additional efforts to be performed.
This item remains open.
4.
Unresolved Items Unresolved items were not identified during the inspection.
5.
Inspector Followup Items (92701)
a
~
(Closed)
Inspector Followup Item 259, 260, 296/83-41-03, Acceptance Requirements for Hanger and Support Settings.
During the previous inspection, NRC inspectors were concerned over the lack of acceptance requirements in procedure N-VT-1 for support settings on spring hangers and snubbers.
The inspector held discussions with licensee's representatives with respect to the above concern and reviewed related document It was noted that revision six of the procedure N-VT-1 had been revised to include the acceptance criteria for spring hangers and snubbers.
This item is closed.
b.
(Closed)
Inspector Followup Item 260/85-51-02, Corrective Actions Resulting from Interim Evaluation of Cable Tray Support Systems.
This item addressed six.fixes as a result of the UE8C's evaluation.
The evaluation was based on the interim acceptance criteria for which the cable tray support systems can sustain the Design Basis Earthquake, and the plant can be brought to a safe shutdown condition.
Further, this item also requested that additional evaluations be performed for Control Bay Mark 31, Mark 10, and Mark 65 Cable tray supports; and Reactor Building cable tray seismic-restraint at the 621 elevation level.
The inspector held discussions with the licensee's representa-tives and reviewed related documents.
It was found that corrective actions with-respect to the aforementioned concerns had been partially completed.
The remaining work is scheduled to be completed by July 1986.
This item is closed.
6.
Procedures and Criteria Review
The inspector reviewed portions of the following procedures and criteria pertaining to IE Bulletin 79-02, IE Bulletin 79-14, and safety-related pipe support and restraint systems to determine whether appropriate procedures and criteria have been established and whether they comply with NRC requirements and the licensee commitments.
a.
Design Criteria BFN-50-D707, Analysis of As-Built Piping Systems, April 17, 1985 b.
BFEB-PI 86-05, NRC-OIE Bulletin 79-02/79-14 Program Document, April 18, 1986 c.
BFEP-PI 85-01, Implementation of NRC-OIE Bulletin 79-02/79-14, January 6,
1986 d.
BFEP-PI 86-06, Implementation of NRC-OIE Bulletin 79-14 Phase II Verification, April 4, 1986 e.
BF MAI-23, Support Installation of Category I Structures, February 7,
1986 f.
Procedure No.
N-VT-l, Preservice and In-service Visual Examination Procedure, June 20, 1985 The above documents appear to be acceptable in terms of meeting NRC requirements and the licensee commitments.
Within the areas inspected, no violation or deviations were identifie 'i
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