IR 05000259/1978029
| ML18024A625 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/30/1978 |
| From: | Brooks E, Andrea Johnson, Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18024A624 | List: |
| References | |
| 50-259-78-29, 50-260-78-32, 50-296-78-30, NUDOCS 7901120016 | |
| Download: ML18024A625 (16) | |
Text
UNITEO STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30303 Report No.:
50-259/78-29, 50-260/78-32, 50-296/78-30 Docket No.:
50-259, 50-260, 50-296 License No:
DPR-33, DPR-52, DPR-68 Licensee:
Tennessee Ualley Authority 818 Power Building Chattanooga, Tennessee 37401 Facility Name:
Browns Ferry Units 1, 2, and
Inspection at:
Browns Ferry Site, Athens, Alabama Inspection conducted:
October 30 - November 3, 1978 Inspectors:
E.
H. Brooks A. H. Johns Reviewed by:
R.
D. Mar in, Chief Nuclear Support Section Reactor Operations and Nuclear Support Branch Da e
Ins ection Summar Ins ection on October 30 - November
1978 (Re ort Nos. 50-259/78-29 50-2 0/78-32 and 50-29 /78-30 gram of pipe support and restraint systems (Units 1, 2, and 3) refueling maintenance (Unit 3).
The inspection involved 65 inspector-hours on-site by two NRC inspectors.
Results:
Of the areas inspected no items of noncompliance or deviations were identifie RII Rpt. Nos. 50-259/78-29, 50-260/78-32 and 50-296/78-30 DETAILS I Prepared by:
E.
H. Brooks, Reactor In ector Nuclear Support Section o.
Reactor Operations and Nuclear Support Branch Da e
Dates of Inspection:
tober 30 - November 3, 1978 Approved by:
R. D. Martin, Chief Nuclear Support Section No.
Reactor Operations and Nuclear Support Branch ate 1.
Persons Contacted
- J. E. Dewease, Plant Superintendent-H. L. Abercrombie, Assistant Power Plant Superintendent-J. L. Harness, (}uality Assurance Supervisor
- R. T. Smith, Mechanical Engineer DE Collins, Mechanical Engineer-G. T. Jones, Outage Director-J.
R. Pittman, Instrument Engineer A. Anderson, Mechanical Engineer-Denotes those present at exit interview.
2.
Licensee Action on Previous Ins ection Findin s Not applicable.
3.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items. of noncompliance or deviations'n unresolved item disclosed during the inspection is discussed in paragraph 5.
4.
Exit Interview The inspectors met with the licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on November 3, 1978.
All items presented in these details were discussed.
With regard to the unresolved item in paragraph 5, the licensee agreed to submit a
written report to the NRC within 30 day RII Rpt. Nos. 50-259/78-29, 50-260/78-32 and 50-296/78-30 I-2 5.
Ins ection of Pi e
Su ort and Restraint S stems The inspectors reviewed the licensee's surveillance procedures and maintenance procedures for safety-related hydraulic and mechanical supports and restraints.
Included in the review were the data and results of all previous inspections and functional testing of hydraulic and mechanical restraints.
Subsequent to review of the procedures, visual inspections were conducted of both accessible and inaccessible (within the drywell) restraints installed in Unit 3, which was in a refueling outage.
Accessible restraints were inspected on Units 1 and 2.
Procedures were reviewed, and inspections conducted as follows:
a
~
Procedures Reviewed SI 4.6.4-Surveillance Instructions for Hydraulic Snubbers M.MD I.45-Mechanical Maintenance Instructions for Removal, Disassembly, Reassembly, and Replacement of Bergen-Paterson and Grinnel Snubbers M.M.I.59-Mechanical Maintenance Instruction - Functional/
Correction M.M.I.59B-M.M.I.59C "
M.M.I.59D-M.M.I.59-1-Grinnel Functional Tests E - System Hydraulic Snubbers Functional Test - Mechanical Snubbers As Found Piston Velocity Measurement and Bleed Result Data - Bergen-Paterson M.M.I.59-2 As Left Piston Velocity Measurement and Bleed Result Data - Bergen-Paterson As a result of the review of the above documents it was concluded that the licensee was in compliance with the surveillance require-ments for hydraulic snubbers as stated in the Technical Specifica-tions as regards acceptability of seal material, inspection interval, and functional testing requirements.
The documents confirm that 1) correction factors are used for temperature dependent functional tests, 2) written guidelines are provided for selection of representa-tive samples for testing, 3) acceptance criteria is identified for
RII Rpt. Nos. 50"259/78-29, 50-260/78-32 and 50-296/78-30 I-3 lock-up rate, bleed rate, piston rod extension, and reservoir fluid level and 4) corrective action is taken to repair or replace inoperable snubbers.
Review of the above procedures disclosed that on unit number 3, four mechanical restraints could not be moved to their extreme ends during testing due to interference with structural grating.
M.M.I-59D requires replacement of the restraints in the event that complete extension of the restraints can not be accomplished.
The data sheet was signed off September 24, 1978, with no indication of corrective action.
This item was identified for future inspection (50-296/78-30-01).
No procedure for inspection of spring hangers was available for review, and the licensee stated that an appropriate procedure is being prepared.
This item was identified for future inspection (50-296/78-30"02).
Following is a summary of the visual inspection and functional testing results as documented by the licensee:
Unit 3 - Visual Inspection Date Ino erable Snubbers Next Ins ection 6-3-76 9-14-77 1-29-78 8<<21-78 Operating Cycle 124 days
+25X 6 months +25/
12 months
+25~
Unit 3 - Functional Testing (4-20-76 to 5-22-76)
Inaccessible snubbers 48 hydraulic snubbers tested 6 snubbers with unacceptable lock-up speeds Accessible snubbers 82 hydraulic snubbers tested 23 snubbers with unacceptable lock-up speeds Unit 3 - Functional Testing (9-16-78 to 9-19-78)
Inaccessible snubbers 3 snubbers tested 0 snubbers inoperable
RII Rpt. Nos. 50-259/78-29, 50-260/78-32 and 50-296/78-30 I-4 Accessible snubbers 7 snubbers tested 0 snubbers inoperable Unit 2 - Visual Inspection Date Ino erable Snubbers 5-25-76 (accessible 6 inaccessible)
8-26-77 '(accessible S inaccessible)
5"25-78 (inaccessible)
7-29-78 (accessible)
1 (accessible)
1 (each)
0 Unit 2 - Functional Testing Date Location Number Tested Number Ino erable 5-17-76 5-17-76 3-26-78 3"26-78 Accessible Inaccessible Accessible Inaccessible
50
5
5
1 Unit 1 - The available documentation was superficially reviewed for inspection and testing results.
No items of noncompliance were apparent.
b.
Ins ections Conducted Accompanied by licensee personnel, the inspectors examined hydraulic and mechanical restraints in all three Browns Ferry reactor plants.
Only Unit 3 drywell was available for inspection of inaccessible snubbers.
While examining hydraulic snubbers on the main steam and feedwater lines within the drywell of Unit 3, grease was discovered on the i
hydraulic reservoir fluid fillfittings of Bergen-Paterson type snubbers identified as SS-B4 and SS-B2.
These fittings are provided for filling the snubber reservoirs with high quality radiation resistant hydraulic fluid.
The presence of grease on these fittings, suggested contamination of the reservoir fluid with general service lubricant.
This condition was reported to Region II management who subsequently obtained agreement from the licensee corporate headquarters that the suspect snubbers would be removed and disassembled for examination of the snubber internals.
While preparing for the disassembly, six additional snubbers in Unit 3 were identified by the licensee to be potentially con-
RII Rpt. Nos. 50-259/78-29, 50-260/78-32 and 50-296/78-30 I-5 taminated.
All eight snubbers were removed from Unit 3.
Results of the disassembly, witnessed by the inspectors, confirmed that general service lubricant had been injected into the reservoir, and had migrated to the control valve and into the snubber cylinder.
It is estimated that the quantity of grease dispersed throughout the unit was in excess of 1/2 cubic inch.
Discussions with the licensee's personnel disclosed that a similar situation had occurred previously, i.e. indications of grease in snubbers, in Browns Ferry Unit 2.
Further review of inspection reports revealed that 16 snubbers on the pressure suppression chamber ring header had indications of grease in the fluid reservoir and had been disassembled, cleaned and reassembled.
The inspectors conducted a follow-up inspection on these snubbers with no adverse findings.
The licensee agreed to remove, inspect and test all known con-taminated snubbers and to investigate with responsible personnel to assure that all contaminated snubbers have been identified and removed.
The licensee agreed to submit a report of the occurrence to the NRC within thirty days which would include a definition of the problem for all Browns Ferry units, and to state the conse-quences and proposed corrective action.
Unresolved Item:
This matter of contaminated snubbers is considered to be an unresolved item subject to subsequent review by NRC.
(50-296/78-30-03)
In addition to the above, the following snubber conditions were noted:
1)
Various snubber ball joints were in need of lubrication.
2)
Snubber SS-5B (Unit 3) - reservoir clamp bolts were missing and the plastic reservoir was in contact with adjacent piping.
3)
Loose clevis to piston rod connects.ons were observed on several snubbers.
4)
Snubber R-42 (Unit 1) - Loose snubber to extension rod bolt.
5)
Mechanical snubber-234 was misaligned and possibly locked up.
6)
Snubber SS4ZA - A nail was used as a substitute for a cotter pi RII Rpt. Nos. 50-259/78-29, 50-260/78-32 and 50-296/78-30 I-6 The licensee agreed to correct the above conditions.
These items will be reviewed at a subsequent inspection.
(50-296/78-30-04)
RII Rpt. Nos. 50-259/78"29, 50-260/78-32, and 50-296/78-30 II-1 DETAILS II Prepared by:
A. H. Jo nson, Reactor Ins ctor Nuclear Support Section No
Reactor Operations and Nuc ear Support Branch Da e
Dates of Inspection:
ctober 30 - N vember 3, 1978 Reviewed "by:
C'.
D.
artin, Chief Nuclear Support Section No.
Reactor Operations and Nuclear Support Branch Da e
1.
Persons Contacted Tennessee Valle Authorit-J.
G. Dewease, Plant Superintendent
- H. L, Abercrombie, Assistant Plant Superintendent-G. T. Jones, Outage Director
- J. L. Harness, (}A Supervisor
- D. Collins, Mechanical Engineer-R. T. Smith, Mechanical Engineer
- J. R. Pittman, Instrument Engineer A. Anderson, Mechanical Engineer W. Ives, Mechanical Engineer J. Miller, Planner R. Shadick, Mechanical Engineer
+Denotes those present at the exit interview.
2.
Licensee Action on Previous Ins ection Findin s Not inspected.
3.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncom-pliance, or deviations.
An unresolved item disclosed during the inspection is discussed in Paragraph RII Rpt, Nos. 50-259/78-29, 50-260/78-32, and 50-296/78-30 II-2 4.
Exit Interview The inspectors met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on November 3, 1978.
The inspectors summarized the purpose and scope of the inspection and the findings.
With regard to the unresolved item in paragraph 5.g, the licensee stated that they were looking into this matter.
5.
Refuelin Maintenance The inspector conducted a
review of the following Unit 3 refueling maintenance activities:
Title 65294 65289 91552 91553 91554 94182 94184 Replace Accumulator Springs in 3 Snubbers in Store Room - HSSA 10 Bergen Paterson Remove, Functional Test and Reinstall Hydraulic Snubbers Suspect Seal and 0-Ring Deteriation Inspection of PSA-10 Snubbers Due Yarway Snubbers Due Inspection MSIV 1-15 Failure of LLRT Valves 1-26, 27 6 1-37, 38 Failure of LLRT 94215 MSIV 1-52 "D" Outboard Failed LLRT b.
Work Plan
. Title 9320 9342 HPCI Turbine Valve PCV-73-43 Replacement Modification MSRV's Modification
RII Rpt. Nos. 50-259/78-29, 50-260/78-32, and 50-296/78-30 II-3 Co Clearance Title 78"1609 78"1611 MSIV Valve Maintenance MSRV Valve Maintenance and Modification d.
HPCI Turbine Re lacement of Tem ora Valve -PCV - 73-43T Inspectors observed and/or reviewed modification replacement of temporary valve PCV-73-43T2 with permanent valve PCV-73-43 per-formed by work plan number 9320 and 225 psig Hydrostatic Test of Associated New Piping.
Inspectors observed plant (}A verification at procedure hold point and noted that there was no apparent leakage.
e.
Maintenance Teardown of Snubber SS-B2 The maintenance teardown of snubber was observed by the inspectors, noting that the approved maintenance instruction was at the work location.
f.
Maintenance Activit Reviews and Acce tance Criteria The Unit 3 refueling maintenance activities of 5.a, 5.b, 5.c, 5.d, 5.e and 5.f above were reviewed by the inspector to verify that:
The maintenance activities were accomplished using approved procedures by qualified personnel.
The required administrative approvals were obtained prior to initiating maintenance activities.
The maintenance activities were inspected in accordance with the licensee's requirements.
Provisions for assuring that system valves, breakers, etc.,
are aligned for normal service.
Provisions for testing equipment following maintenance.
The inspector used one or more of the following acceptance criteria for the above items:
Technical Specifications Final Safety Analysis Report
RII Rpt. Nos. 50-259/78-29, 50-260/78-32, and 50-296/78-30 II-4 ANSI 18.7-1972 Operating equality Assurance Manual BFA 45 - Trouble Reports BF 6.1 - Performance of Maintenance BF 6 '
- Identification of Corrective Maintenance g.
F~indin n
The inspector found that the following trouble reports were missing the indicated documentation:
Title 65294 Replace Accumulator Springs in 3 Snubbers in Store Room - HSSA 10 Bergen Paterson F~indin Missing Supervisor Initials 65289 Remove, Functional Test and Reinstall Hydraulic Snubbers Missing Supervisor Initials 91552 Suspect Seal and 0-Ring Deteriation Missing Supervisor Initial 91553 Inspection of PSA-10 Snubbers Due Missing Supervisor Initials 91554 Yarway Snubbers Due Inspection Missing Supervisor Initials 94182 MSIV 1-15 Failure of ILRT 94184 Valves 1-26, 27 and 1-37,
Failure of LLRT Missing Operations Work Authorized by Signature Missing Operations Work Authorized by Signature
RII Rpt. Nos. 50-259/78-29, 50-260/78-32, and 50-296/78-30 II-5 94215 MSIV 1-52 "D" Outboard Failed LLRT Missing Operations Work Authorized by Signature Standard Practice BPA 45 Trouble R~e orts requires the above initials and signatures.
However, the licensee stated that BF 6.2 Identifi-cation of Corrective Maintenance does not require the initials and signatures and that the Trouble Reports are used only as identifi-cation of components requiring corrective maintenance.
This is an apparent conflict between BFA 45 and BF "'6.2 which are Standard Practices used to implement the Operation equality Assurance Manual at Browns Ferry.
Unresolved Item:
This matter of apparent conflict between standard practices BFA 45 and BF 6.2 is considered an unresolved item pending the review by the inspector with his management and further review at the next maintenance inspection (296/78-30-05).