IR 05000259/1976010
| ML18283B621 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/23/1976 |
| From: | Gilleland J Tennessee Valley Authority |
| To: | Moseley N NRC/RGN-II |
| References | |
| IR 1976010 | |
| Download: ML18283B621 (25) | |
Text
~p&T1 py z'~re-19<e 830 Power Buildin ENNESSEE VALLEY AUTH ITY CHATTANOOGA.
TENNESSEE 37401 June 23, 1976 Q xawa@/o Mr.Norman C.Moseley, Director Office of Inspection and Enforcement U.S.Nuclear Regulatory Commission Region II-Suite 818 230 Peachtree Street, NWo Atlanta, Georgia 30303
Dear Mr.Moseley:
This'is in response to P.J.Long's June 3, 1976, letter, IE:II:BJC 50-259/76-10, 50-260/76-10, which transmitted for our review an IE Inspection Report (same number)o We have reviewed thatreport and do not consider any part of it to be proprietary.
Very truly yours J.E.Gilleland Assistant Manager o Power An Equal Opportunity Ernpioyer Cl~(~I Q>
.~~PR AK00.-t'P~++*++In Reply Refer To: IE:II:BJC 50-259/76-10 50-260/76-10 UNITEO STATES NUCLEAR REGULATORY COMMISSION REGION II 230 REACHTREE STREET.N.W.SUITE 818 ATLANTA, GEORGIA 30303 JUN 3 SN Tennessee Valley Authority ATTN: Mr.Godwin Williams>Jr.Manager of Power 830 Power Building Chattanooga, Tennessee 37401 Gentlemen:
This refers to the inspection conducted by Mr.B.J.Cochran of this office on April 21-23 and April 28-30, 1976, of activities authorized by NRC Operating License Nos.DPR-33.and DPR-52 for the Browns Ferry Units 1 and.2 facilities, and to the discussion of our findings held with Mr.J.R.Hilding during the inspection.
Areas examined'uring the inspection and our findings are discussed in the enclosed inspection report.Within these axeas, the inspection consisted of selective examination o'f procedures and representative records, interviews with personnel, and observations by the inspector.
Within the scope of this inspection,.
no items of, noncompliance were disclosed.
We have, examined actions you have taken with regard to previously identified enforcement matters.These are identified in Section II of the summary of the enclosed report.In accordance with Section 2.790 of the NRC's"Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the enclosed inspection report vill be placed in the NRC's Public Document Room.If this report contains any information that you believe to be proprietary, it is necessary that you submit a written application to this office requesting that such information be withheld from public disclosure.
If no proprietary information is identified, a written statement to that effect should be submitted.
If an application is submitted, it must~fully identify the bases for which information is claimed to be proprietary.
The application should be prepared so that information sought to be withheld is incorporated in a separate paper.and referenced in the application since the application vill be placed
~i Qi~>J Tennessee Valley Authority in, the Public Document Room.Your application, or written statement, should be submitted to us within 20 days.If we are not contacted as specified, the enclosed report and,this letter may then be placed in the Public Document Room.Should you have any questions concerning this letter, we will.be glad to discuss them with you.Very truly yours, F.J.Long, Chic Reactor Operations and Nuclear Support Branch Enclosure:
IE Inspection Report Nos.50-259/76-10 and 50-260/76-10
~I II II~CO, (4 P 0+*i+>>UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 230 PEACHTREE STREET, N.W.SUITE 818 ATI ANTA, GEORGIA 30303 IE Inspection Report Nos.50-259/76-10 and 50-260/76-10 Licensee: Tennessee Valley Authority 818 Power Building Chattanooga, Tennessee 37401 Facility Name: Docket Nos.: License Nos.: Category: Browns Perry Units 1 and 2 50-259 and 50-260 DPR-33 and DPR-52 c/c Location: Limestone County, Alabama Type of License: GE, 1098 Ewe, Bt&Type of Inspection:
Pire Damage Restoration Dates of Inspection:
April 21-23 and 28-30, 1976 Dates of Previous Inspection:
April 5-9, 1976 Principal Inspector:
B.J.Cochran, Reactor Inspector Projects Section Reactor Construction and Engineering Support Branch Accompanying Inspector.:
T.D.Gibbons, Reactor Inspector Engineering Support Section No.1 Reactor Construction and Engineering Support Branch Other Accompanying Personnel:
S.D., Ebneter, Acting Section Chief Engineering Support Section No.1 Reactor Construction and Engineering Support Branch
~I 0 Qi IE Rpt.Nos.50-259/76-10 and 50-260/76-10 Prncipal Inspector:
B.J.Cochxan', Reactor Inspector Projects Section Reactor Construction and Engineering Support Branch ajar~/gg Date Reviewed by: J.C Bf ant, hier'ro cts Section Reactor Construction and'ngineering Support Bxanch Date 0~~~i IE Rpt.Nos.50-259/76-10 and 50-260/76-10 SUMMARY OF FINDINGS I.Enforcement Items None II.Licensee Action on Previousl Identified Enforcement Matters 76-4-Al(II)
Audits Audit schedules were not updated at the required frequency, and there was no documented'vidence that audits are con-ducted in accordance with an audit plan.This item is closed.(Details I, paragraph 3)76-4-A2(II)
Cable Minimum Bend Radius A cable was installed in Unit 2 in violation of the minimum bend radius.This item is closed.(Details I, paragraph 4)III.New Unresolved Items None IV.Status of Previousl Re orted Unresolved Items None None VI.Unusual Occurrence None 4 VII.Other Si nificant Findin s~None VIII.Mana ement Interview/During this inspection period, the inspectors were in continuous communication with the Browns Ferry management and as there were no items of noncompliance or unresolved items identified, no exit interview was held.
41 Oi IE Rpt.Nos.50-259/76-10 and 50-260/76-10 DETAILS I Prepared by: B.J.Cochran, Reactor Inspector IP Projects Section Reactor Construction and Engineering Support Branch-~/i)i Date Dates of Inspection:
April 21-23, 1976 April 28-30, 1976/Reviewed by: J.Bryant, hief Pr ects Section Reactor Construction and Engineering Support Branch Date All information in Details I applies equally to Units 1 and 2 except where identified with a specific reactor.1.Individuals Contacted Tennessee Valle Authorit (TVA)H.J.Green-Plant Superintendent J.R.Hilding-Fire Restoration QA Manager T.G.Campbell-Modification and Additions Unit Supervisor J.E.Law-QA Engineer D.Wright-Electrical Engineer T.Ziegler-Mechanical Engineer 2.General a~Cleanup of major components and equipment from fire residue is essentially completed.
Major effort in the Units 1 and 2 reactor building is centered around rebuilding of firestops and electrical penetrations, and applying Flameastic to exposed cables in open.trays.b.As a result of inspection of installed SBM control switches TVA has discovered extensive failure of the cam follower and moving contact assembly.There was no reported total failures that would render the switch inoperable but investigation has shown the plastic cam follower crazed and broken.
IE Rpt.Nos.50-259/76-10 and 50-260/76-10 I-2 TVA has initiated an extensive investigation to determine the extent of the damage prior to establishing the corrective program.3.Audits (76-4-Al(II During a previous inspection, it was determined that audit schedules were not updated at the required frequency and there was no documented evidence that audits were conducted in accordance with an audit plan.An audit schedule identifying fire restoration activities was issued to be performed commensurate with the work activity.The Office of Power Quality Assurance Procedure No.OP-QAP-18.1 issued March 3, 1976, now requires a written response within 30 days to audit reports which identify noncompliances by the audited organization.
Audit report OPQAA-76-SP-1-(3)
performed on March 16-18, 1976, covering"Browns Ferry Nuclear Plant Fire Damage Repair and Return to Sexvice Penetration Seals, Firestops and Application of Flameastic," was reviewed and found to be complete in all the areas previously identified as being deficient.
Based on the foregoing information the infraction response is considered to be adequate and the noncompliance closed.4.Cable Minimum Bend Radius 76-4-A2(II Previous inspection revealed a cable installed in Unit 2 was in noncompliance with the minimum bend radius.The licensee reported the infxaction was corrected on March 2, 1976.In addition the licensee committed to initiate work plans to make final inspections and correct any noncompliances that may have resulted from work performed immediately following the fire.This response is considexed to be adequate and the noncompliance is closed.5.TVA Restoration Plan Commitments a.In Part II, Section G of the Restoration Plan the QA and Audit staff is committed to conduct audits of each major phase in the plant recovery schedule.
IE Rpt.Nos.50-259/76-10 and 50-260/76-10 I-3 Inspection has confirmed that audits are being performed and the TVA letter of March 15, 1976, provides the schedule for future audits of the recovery program.b.Part VIII, Section A.l of the Restoration Plan provides procedure DED-EP 21.15, to establish a procedure for identifying and evaluating mechanical equipment which could have been exposed to unanticipated transient loadings resulting from maloperation of Units 1'and 2 equipment.
The Browns Perry Mechanical Maintenance Instructions (MMI)46 and 53'ere implemented to inspect and evaluate corrosion damage to piping and mechanical components resulting from fire residue and to perform NDE of pipe and tubing.The final reports of work performed and inspected in accordance with these instructions were inspected and found to be in order.There are no further questions regarding these items at this time.C~In Part VIII, Section B.l, TVA committed to determine the temperatures in the fire zone and adjacent areas and effects on equipment.
In response to this commitment, Report No.CB-75-12 was issued identifying the approximate temperature zones as derived from an examination and analysis of physical evidence within, the zones.As a result of this study six temperature zones were established.
Each zone was identified and inspected by the NRC inspector and physical evidence listed in the report was confirmed.
Information received as a result of this study was used to establish criteria for inspection and testing of structural members and equipment.
There are no further questions regarding this study at this time.d.The Restoration Plan includes criteria for (BFN-50-D-703)
Evaluating Structural Steel Components/Evaluating Reinforced Concrete Structures (BFN-50-D704)
and Evaluating Mechanical Piping, HVAC Ducting and Piping Components (BPN-50-D705).
IE Rpt.Nos.50-259/76-10 and 50-260/76-10 I-4 On March 22, 1976, TVA issued the concluding report (CEB-76-7),"Program for Identification and Evaluation of Affected Structure and Mechanical Equipment." This report covers the identification, evaluation and restoration of such equipment as valves, pipes, hangers, restraints, HVAC ducts and supports, cable trays and supports, conduits, building features, penetra-tion bulkheads and cooling equipment that were physically located within the fire zone or were affected by conditions resulting from the fire.The report identifies the following equipment as being replaced: (1)cable trays;(2)tray supports;(3)pipe supports;(4)expandable bolt anchors;and (5)embedded.steel anchor plates.The NRC inspectors observed work performed in each of the areas plus reviewed the embedded anchor test results.The removal of concrete core and reinforcing steel samples plus the repair of the spalled concrete in accordance with the documented procedures was observed.In addition to the above listed equipment the following equip-ment was replaced: (1)6 inch aluminum spent fuel rod cleanup lines;(2)electrical conduit in fixe zone;(3)portion of 36" x 36" HVAC exhaust duct;(4)uninsulated carbon steel floor drain;(5)4 inch uninsulated carbon steel fire protection line;(6)3 inch aluminum demineralized water line;(7)3 inch carbon steel service air line;(8)4 inch aluminum demineralized water line;and (9)all copper instrument lines.in fire zone.e.Based on information in this report plus inspection of records of work performed on the above listed equipment, there are no further questions regaxding these items at this time.Part X, Section A of the Restoration Plan commits TVA to the removal of the remote indicating light circuits on both the AC and DC MOV boards.The removal of the lights was specified under.Work Plans WP-4676 and WP-4682.The work plans and inspection reports were inspected and determined to be complete.Part X, Section A of the Restoration
'Plan commits TVA to change the DC control power to the 4KV shutdown boards so only one supply is required for the board to be operational but a second supply will be available via manual transfer if needed.
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0 IE Rpt.Nos.50-259/76-10 and 50-260/76-10 I-5 The change was specified under Work Plan WP-4343.The work plan and inspection reports were inspected and deter-mined to be complete.g.Part X, Section A of the Restoration Plan commits TVA to reclassification of the 4KV feeders into Division I or Division II to provide separation in a tray or conduit for each normal 4KV supply to the four 480V shutdown boards 1A, 1B, 2A and 2B, and the two 480V diesel auxiliary boards A and B.This change was specified under Engneering Change Notice 9047 and Work Plans WP-4688, WP4689, WP4691, WP4690, WP4716, WP4798, and WP4797.The work plans and inspectiom reports were inspected and determined to be complete.
'I~il 4~it IE Rpt.Nos.50-259/76-10 and 50-260/76-10 II-1 DETAILS II Prepared by: T.D.Gibbons, Reactor Inspector Date Engineering Support Section No.1 Reactor Construction and Engineering.Support Branch Dates of Inspection:
April 21-23 and 28-30, 1976 Reviewed by.T.,E.Conlon, ief Engineering Support Section No.1 Reactor Construction and Engineering Support Branch Date The discussion contained in this section of this report applies to Units 1 and 2 equally unless noted otherwise.
1.Persons Contacted Tennessee Valle Authorit (TVA}J.Hilding-QA Restoration Manager, OPQA E.Law-QA Engineer, OPQA D.Alley-Electrical Engineer, DEC B.Gant-Construction Engineer, DEC D.Jent-Electrical Engineer, DEC 2.Installation of,Flamemastic in the Reactor Buildin s The inspector observed'the completed application of Flamemastic on the secondary containment areas in Units 1 and 2 on elevations 621 and 639.At elevations,621, Unit 1, tray segments inspected included trays TL, LE, AG, MN, MM and BB.At elevation 639, Unit 1, the three longest trays (FU, MO, NM)were inspected as typical.In Unit 2 at elevation 621 the following trays were typical of the total installation trays NH, NO, CL, GC, LF and TM.At elevation 639, Unit 2, the trays typifying the installation included FU, NN, BY and BJ.The installation on the trays appeared to conform to the requirements of procedure BF-206R,"Electrical Penetration Seal and Firestop Installation and Inspection (Units 1 and 2, Browns Ferry Nuclear Plant)," Rev.0.Work is proceeding on elevation 593 in both units.TVA's QC is following the installation and data sheets are being signed.The inspector did not identify any noncompli-ances.Inspection of this woxk will continue.
IE Rpt.Nos.50-259/76-10 and 50-260/76-10 II-2 3.Penetration Seals and Firesto s In Part X, Section A of the Browns Ferry Nuclear Plant Restoration Plan, TVA committed to a program using new material in all future seals, all breached seals{unless replacement would cause damage to the cables), and to upgrade existing penetrations to present design or replace with new material in accordance with design.The in-spector observed 251 penetrations in various states of completion in the control rooms.Procedure BF206R and its data sheets con-trolled the work.The typical details fox this area are D&E on drawing 45N830-27.
The inspector observed the installation of the silicone foam in penetrations C92, C93 and C94.The relay room penetrations were installed in accordance with Figure E of 45N830-27 and sketchs which were approved by DED.There were a total of 58 type E penetrations and 22 penetrations defined by ECN 9057.The latter 22 penetrations are used for the spare penetrations in the floor and include a steel plate to protect the seal from mechan-ical damage.The inspector observed the installation of seals and firestops in various areas in the plant including nine Figure A types (C, H, I, J, K, L, V, K and Y)which were in various stages of construction.
Additional.seals.and firestops were inspected throughout the plant;such as (Al, 4, 5, 16, 17,'26, 27, 28, 33, 34, B2, 10, ll, 12, 17, 18, 26).There were two firestops that had damaged Marinite boards, which the licensee's QA reported.These fixestops were B12, elevation 621, and B26, elevation 639.In all cases a data sheet was signed for each step of repair.Step 7.1.1 and 7.4.3.1 of BF 206R requires removal of the urethane material to a level of acceptability.
The inspector noted that conduits were being instal-led in most penetrations so that additional cable may be installed without breaking the seal.It was noted that the barrier plates and conduits in the penetration were given a 1/8-inch (dry)coating of.Flamemastic.
There were no items of noncompliance identified.
.4.Reroutin of ESF Cables Tra and Conduit Outside the Fire Boundar Zone The inspector reviewed fifteen work plans which define the work and included the necessary details for work accomplishment, and the necessary signatures.
The work plans reviewed were 4330, 4331, 4332, 4334, 4335, 4342, 4344, 4350, 4351, 4352, 4352R1, 4629, 4646, 4652 and 4395.These work plans were generated to incorporate the requirements of ECN L-9048.Approximately 125 cables and 26 conduits have been relocated.
This work is.almost complete.Construction and QC will make a final review of the installation.
The IE:II inspector will review the work when it is completed.
0 i>Qi IE Rpt.Nos.50-259/76-10 and 50-260/76-10 II-3 5..Cardox Pire Extin uishin S stem The inspector observed that the Cardox fire extinguishing system was available for use in the Units 1 and 2 spreading rooms.The inspector verified that there were no physical obstacles preventing the manual operation of the system.
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