ML20010H503
| ML20010H503 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/09/1981 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| IEB-79-02, IEB-79-14, IEB-79-2, NUDOCS 8109240547 | |
| Download: ML20010H503 (4) | |
Text
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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNbS$EE [374o1
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400 Chestnut Street Tower II gr y, g1 S t Mr. James P. O'Reilly, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region II - Suite 3100 101 Marietta Street Atlanta, Georgia 30303 Denr Mr. O'Reilly:
OFFICE OF INSPECTION AND ENFORCEVENT BULLETINS 79-02 AND 79 BROWNS FERRY NUCLEAR PLANT UNIT 3 296 In an August 7, 1981 telephone conversation with menbers of your staff, TVA was requested to provide the results of the evaluations performed upon completion of each unit's inspections for the subject bulletins.
In response to this request, the enclosed table summarizes the resolution of all significant discrepancies discovered during the Browns Ferry unit 3 inspections.
As indicated in this table, all safety problems discovered to date have been corrected, and other discrepancies have been scheduled for resolution.
If you have any questions, please call Jim Domer at FTS 857-2014 To the best of my knowledge, I declare the statements contained herein are complete and true.
Very truly yours, TENNESSEE VALLEY AUTHORITY c CD @~
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M. Mi is, fianager Nuclear Regulation and Saf 3
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U.S. Nuclear Regulatory Commission Washington, DC 20555
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RESOLUTIONS FOR SIONTFICANT DISCREPANCIES BROWNS FERRY NUCLEAR PLANT UNI? 3 (See Footnotes at End of Table)
Finai Initial Evatuation Problem Evaluation After Analysis Proposed Problem
. System Description (Seismic)*
(Category)*
Resolution Number 0901-002 EECW Restraint R-56 missing 1
Not r3 quired Line requirinR Complete restraint was removed 1212-002 EECW Anchorage on R-8 FS tess 2
Not required Restore anchorage than 2.0 021381-001 EECW Line will not qualify 2
3 Install additional restraints by criteria 070180-001 EECW Poor restraint spacing 3
3 Additional supports 021381-002 EECW Line will not qualify by 3
Reanalysis
. criteria 101080-001 EECW and Anchorage of piping in 1
2 Redesigned restraints
' Complete and anchors installed RHRSW service water tunnel 101180-001 EECW and Leakaee of coupling 2
2 Redesign restraint RHRSW due to preload by restraint 122280-001 RHR SpriEg hangers' pinned 2
4 Unpin hangers 012181-001 RHR Broken plate on spring 2
Not required Repair or replace broken plate hanger N-149 1014-001 HPCI Restraint R-46 1
Not required Repaired / Corrected.
Complete condition causing distressed distress
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Final Initial Evauetion Problem Problem Fvaluation After Analysis Proposed Number System Description (Seisnic)*
(Category)*
Resolution 1027-001 HPCI Pestraint R-32 failed 1
Not required Redesigned restraint.
Complete in service Corrected condition causing failure.
080780-001 Control Rod Scram header unrestrained 2
2 Redesign restraints Drive Return along tongitudinal axis 022280-04 FPC Support H-7.
Drawing 1**
Not required Insta11 design calls for 1-1/2-inch-support diameter rod, but 1/2-inch-diameter rod was installed.
0111-002 FPC Hanger H-6 damaged.
2 Mot required Remove H-6 Redundant support.
072180-001 RBCCW Restraint R336-MK25C-2 3
Additional supports overloaded 011080-001 RBCCW Missing and relocated 3
Not required Reanalysis restraints 071680-01 RBCCW Hanger H-82.
Support 3
Not required Return to design is connected on one condition side; nut missing on other side.
1217-001 RBCCW Restraints R-19 and 3
3 Add supports R-39 lock axially 072480-004 RBCCW No lateral restraint 3
a None required between floor penetrations 011880-003 Radwaste Restraint spacing 2
4 None required 3 ump Panel from X19 to pump Discharge 041480-117 CSS Ring Hangers not qualified 2
Not required Restore to design
-118 Header to design loads
-119
-121
-126
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- i e
Tha anaivsis/evasuation
'Catemory 1.
t'nacceptable. T*chnical specifications covern sebaduAine of ebinres.
for loss of pressure boundary, Aoss of containment indicates that there is a definite potential or other conseq'teace, such as improper slope or a missing valve, which has an unacceptable
- seat, effect on plant safety or r fstem function. The effect on plant safety is determined by a safety review.
Changes witi be made as soon as feasible. (The analysis /
Temporarily approved - Priority 1.
evaluation indicates that changes should be given priority over those indicated in category 3.)
' Category 2.
' Category 3.
Temporarity oproved - Priority 2.
Changes will be made on a normat schedule. (The analysis /
be made on a normal schedule.)
evaluation indicates that changes may (The analv -is/ evaluation indicates that intensified stresses in the Field channes not required.
' Category 4.
as-built configuration do not exceed vode allowable stresses.)
review has shown that plant safety and system function were not impaired,
A safety s