IR 05000259/1976015: Difference between revisions

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{{Adams
#REDIRECT [[IR 05000259/1976016]]
| number = ML18283B614
| issue date = 08/05/1976
| title = Responding to Letters of 8/2 & 8/3//1976, Referring to IE Inspection Reports for 50-259/76-15 & 76-16, & 50-260/76-15 & 76-16, Letter Advising No Proprietary Information Is Contained
| author name = Gilleland J E
| author affiliation = Tennessee Valley Authority
| addressee name = Moseley N C
| addressee affiliation = NRC/RGN-II
| docket = 05000259, 05000260, 05000296
| license number = DPR-033, DPR-052, DPR-068
| contact person =
| document report number = IR 1976015, IR 1976016
| document type = Inspection Report, Letter
| page count = 25
}}
 
{{IR-Nav| site = 05000259 | year = 1976 | report number = 015 }}
 
=Text=
{{#Wiki_filter:TENNESSEE VALLEY AUTHORITY Ctlh fTF 400oA't EtiNEssEK'74C1 August 5, 1976~i~g.'),i)(~g f):).);;r J~~4!!r, Norman C.!Ioseley, l)irector Office of Inspection and Enforcement U.S.I'uclear Pet,ulatory Commission 3'egion II-Suire SlU 230 Peacbtx ee Street, h4.Atlanta Georgia 30303 7 9nar Hr.Hoseley::!is is in response to your August 3, 1976, le rer, IH:II:D3C S0-259/76-Ig 50-260/76-~
i'iiicn t.ransmit:ted for our reviei: an IF.Inspection Report (same number};and t.o F.3~l.on)'s August 2, 1976, letter, I:-;:II:RPS 50-259/76-15, 50-260/76-15, which transmitted for our revic~an IF.inspection Report (same nut.ber).~e have revieved t.hose reports and do not consider any part of them to be proprietary.
 
Very truly vo s, u'-.T., Gilleland/~.=ŽAssistant Hanover of Pover
~g0 8E0Ij P O Op pW~0 e.n+**++In Rep1y Refer To: IE:II:RFS 50-259/76-15 50-260/76-15 UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 230 PEACHTREE STREET, N.W.SUITE$18 ATLANTA, GEORGIA i30303 AVG 3'l976 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 Messrs.D.G.Hinckley, A.D.Kowalczuk and R.F.Sullivan of this office on June 16-25 and July 1-5, 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 Messrs.Green, Dewease, and Denton at the conclusion of the inspection.
 
The inspection was an examination of the activities conducted'nder your" license hsIthey relate'o radiation safety and to compliance with the Commission's rules and regulations and the conditions of your license.The inspection consisted of selective examination of procedures and representative records, interviews with personnel, and observations by the inspector.
 
During the inspection, it was found that certain activities under your license appear to be in noncompliance with NRC requirements.
 
These items and references to pertinent requirements are listed in Section I of the summary of the enclosed report.Corrective.
 
actions to:prevent recurrence were completed prior to the conclusion of this inspection; therefore, a reply to these items of noncompliance is not requested.
 
In accordance with Section 2.790 of the NRC's"Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of thi's letter and the enclosed inspection report will be placed in the NRC's Public Docu-ment 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
,e 0
~Tennessee Valley Authority 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 will be placed 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, T.J.Long,'Chi Reactor Operations:and Nuclear Supp'ort Branch.
 
===Enclosure:===
IE Inspection Report Nos;50-.259/76-15 and.50-260/76-15
~~Qi 8'IK0(P 0 ey++*++UNITED STATES NUCLEAR REGULATORY COMMISSION.
 
REGION II 230 PEACHTREE STREETe N W SUITE SIS ATLANTA'EORGIA 30303 ,IE Inspection
'Report,Nos.,50-259/76-15 and 50-260/76-15.Licensee:
Tennessee Valley, Authority 830 Power Building Chattanooga,'Tennessee 37401 Facility Name:.Browns Ferry 1 and.2 Docket Nos: 50-259 and 50-260 License Nos.: DPR-33,, DPR-52 Location: Limestone.County', Alabama Type of License: ,3293 Mwt, BVR (GE)Type of Inspection:
Routine, Unannounced, i'\~Dates of.Inspection:
June.16-25,.July 1-5, 1976 3.Dates of Previous Inspection:.
May 20-21,.25-28, June 2-4, 1976"-Principal
'.Inspec'tor:
R.F.'Sullivan, Reactor.Inspector (June,,'23-25, July 1'-5)Inspectors-in-Charge:.D.G.Hinckley, Reactor Inspector (June 19-.'22)Reactor Projects Section No.1 Reactor Operations and'uclear Support Branch A.D.Kowalczuk, Radiation Specialist (June, 16-18)Radiation.Support Section Fuel Facility and Materials Safety Branch Accompanying Inspectors:
G.R.Klingler, Reactor Inspector Reactor.Projects Section No..1 Reactox Operations an'd Nuclear Support'Branch J.E.Ouzts, Reactor Inspector Nucleax Support Section Reactox Operations.and'.Nuclear Support Branch
~I 41 IE Rpt.Nos.50-259/76-15 and,50-260/76-15 Principal Inspector:
C.R.F.Sullivan, Reactpr Inspector Reactor Projects Section No.1 Reactor Operations and Nuclear Support Branch Reviewed by: C L'.C.Dance, Chief Reactor Projects Section No.1 Reactor Operations and Nuclear Support Branch Da e II
~IE Rpt.Nos.50-259/76-15 and 50-260/76-15 SUMMARY OF FINDINGS I.Enforcement Items Infraction Contrary to Technical Specification 4.3.C, the water supply valves 85-612 and 85-615 to hydraulic control unit 30-3l,were not open during refueling operations on June 19, 1976.(Details I, paragraph 3)II.Licensee Action on Previousl Identified Enforcement Matters None III.New Unresolved Items None IV.Status of Previousl Re orted Unresolved Items Not inspected.
 
V.Unusual Occurrences None VI.Other Si nificant Pindi s Unit 2'uel Reloadin Pull core reloading of 764 fuel bundles was completed July 4, 1976.Unit 1 Fuel Reloadin Reloading of Unit 1 was begun on July 4, 1976.VII.Mana ement Interview The results of the inspection presented in the details of this report were discussed with site personnel in,separate meetings.at the end of each inspection visit as follows': 'June.18-Mr.Green June 29-Mr.Dewease July 5-Mr.Denton 41 IE,Rpt.No.50-259/76-15 II-1 DETAILS II Prepared by:.A.D.Kowal zuk, Radi on Specialist Radiation'pport Sect on Fuel Facility,and Materials'afety Branch Da e Dates of Inspection:
Jun 16-18, 1976 Reviewed by: z)~~~A.F.Gi son, Section Chief Radiation Support Section Fuel Facilities.and Materials Safety Branch Date 1.Individuals Contacted H.J.Green-Plant Superintendent R.G.Metke-Results Supervisor W.C.Thomison-Chemical Engineer M.L.McNeely-Chemical Engineer J.T.Dills, Jr.-Chemical Engineer G.Brantley-.Chemist W.Kinsey-Mechanical Engi'neer L, Coots-Nuclear Engineer W.Haley-Electrical Engineer 2.Control Room Emer enc Ventilation S stem Records of tests'equired by Technical Specifications 3.7.E and 4.7.E were exami'ned.
 
Testing o'f.trains A and B appeared'to be complete with satisfactory results.Dampers FCC-150-31-A and C listed'n the Technical Specifications have been removed due to a design change.Management representatives stated that a Technical Specification change would be submitted for approval.Drawing 47W931-3 appears to confirm removal of the dampers.This change did not require prior Commission approval as Interim Technical Specifications not requiring this system were in effect.3.Standb Gas Treatment S stem SBGT Results of testing required by Technical Specifications 3.7.B and 4.7.B were examined by the inspector.
 
Testing appeared to be complete with satisfactory results on trains A and B.4.Waste Processin.S stem Additions The inspector observed that the construction of a liquid waste evaporator and a urea formaldehyde solidification system being added to the radioactive waste processing systems was near completion.
 
A management representative stated that startup testing would be initiated in the near futur E Rpt.No-50-260/76-15 DETAILS I Prepared by:.r/Ouzts,reactor Inspector Nuclear Support Section Reactor.Operations and.Nuclear Support Branch 8(mi-/': D-G.Hinckley, Reactor Inspector Reactor Projects Section No.1 Reactor Operations and Nuclear'Support Branch S~~Z"!i Date 7 Dkte.Dates of Inspection:
June 19-22, 1976 Reviewed by: H.C.Dance, Chief.Nuclear Support Section Reactor Operations:and Nuclear Support Branch~9~7C Date 1.Personnel Contacted H.J.Green-Plant Superintendent W.A.Conley-Shift Engineer J.G.Dewease-Assistant Plant Superintendent T.W.Jordan-Sr.Reactor Operator J.A.Matooth-Shift Engineer G.T.McChristian
-Reactor.Operator R.W.McDowell-.Reactor Operator R.G.Metke-Results Supervisor J.C.Newborne-Sr.Reactor Operator B.L.Roth-Shift Engineer J.B.Studdard-Operations" Supervisor 2.Witnessin Puel Loadin Licensee Amendment No.20 to permit fuel loading was authorized on June 18, 1976.Initial Unit 2 fuel loading and reactivity monitoring operations conducted by the two fuel loading shifts were witnessed on June 19, 20 and 21.During the witnessing'of these operations, no deficiencies were observe IE Rpt.No..50-260/76-15 I-2 ,3.Review of Prere uisites and Plant Conditions Prerequisites and plant conditions required by the technical specifications and fuel loading procedure were verified.As a result of.these verifications, one item of noncompliance was observed.Two stop valves, 612 and 615, for hydraulic control unit 30-31 were found shut and should have been open as required by the Ghchnical Specification 4.3.c.These shut valves were brought to the attention, of operating personnel by the inspectors and the.condition was corrected.
 
The licensee subsequently reported this matter,in a letter.to the NRC dated 7/2/76.This item is close IE Rpt.Nos.-50-259/76-15
~~and'50-260/76-15 III-1 DETAILS,III Prepared.by::R.F.Sullivan, Reactor Inspector Reactor Projects Section No.1 Reactor Operations and Nuclear Support Branch Date'Dates of Inspection:
June 23-25, July 1-5,.1976 Reviewed by: '.H.C..Dance, Chief Reactor Projects Section No.1-Reactor Operations and Nuclear Support Branch 7 3c.1.Persons Contacted H.J.Green-Plant Superintendent.J.G'.Dewease-Assistant Plant Superintendent
:J.B.Studdard-Operations Supervisor R.Hunkapiller
-Assistant Operations Supervisor T.P.Bragg-QA Staff'Supervisor G.T.Denton-Shift Engineer J.C.Mewbourne-Assistant Shift Engineer T.W.Jordan-Assistant Shift Engineer W.E.Brown-Assistant, Shift: Engineer 2.Unit 2 Fuel Loadin Reloading of fuel into the Unit 2 reactor vessel began on June 19, 1976, which was observed by IE inspectors as.reported in Details I of this report.Additional witnessing of fuel loading was.done by other inspectors on June 23, 24, 25, July 1, 2 and 3, 1976.Observa-tions included control room activities associated with fuel'oading as, well as the actual fuel handling on the refueling floor.Portions of operations conducted by both day and night refueling crews were~observed.The full core loading of 764 bundles was completed at 3:20 a.m.on July 4.The inspectors observed no deficiencies in fuel loading operation ~I 0 f~I
~IE Rpt.Nos.50-259/76-15 and 50-.260/76-15 III-2 3.Restoration Prefuel Loadin Functional Test Pro ram-Unit 1 Phase I Cold Functional Testin'The planned.functional testing of components and systems was completed with no, exceptions.
 
b.Phase II Surveillance Testin The purpose.of this phase was to reestablish the plant surveil>>lance program for Unit 1.The program was based on.the proposed Technical'pecifications for the restart of Units 1 and 2 which was consistent with.the program described in the'Recovery Plan.'here was a total of 217 tests listed on this program.All but 12 were successfully completed by, July 2, 1976.The 12 were considered not necessary for fuel loading and were scheduled for completion prior to startup.PORC made a final review of Phase II on July 2, 1976, and concurred in the exception list.'The inspector rev'iewed the status of the test program and con-firmed the completion of all except the 12 tests previously mentioned.
 
The inspector confirmed that the systems involved in these 12 tests would'ot.affect fuel loading.The test data package for 48 individual tests were selected at random for detailed review by the.inspector.
 
Results indicated that criteria were.met and that.any listed exceptions were satisfied.
 
C~Phase III Master.Checklist The master checklist had been completed up to the step where the Plant Superintendent authorized fuel loading which was being held up until he received NRC authorization to load fuel.*Exception items were listed with the basis given:for not needing completion for fuel loading.The inspector con-curred that all exception items dealt with systems or components not required fo''uel, loading.Based on the inspectors observations relating to the retest program and the prefuel loading functional"test program, they telephoned the IE:II office on July 2',:to forward their findings which supported plant readiness to load fuel only in Unit l." 4.Unit 1 Fuel Loadin The.license for Unit 1 was amended July 2, 1976, to authorize fuel reloading only with control rods disabled in the full in position as was the case for Unit ~i IE Rpt.Nos.50-259/76-15.and 50-260/76-15 III-3 Inspectors witnessed fuel loading activities on July 4 and 5 which included inserting the first bundle at 3:18 p.m.on July 4.Selected operations were observed in the control room and refueling floor on both day and night shifts.The inspectors noted that activities were in conformance with written procedure SRI 3'hich covered the special loading operations required by'he license amendment.
 
The prerequisites for fuel loading were satisfied and the inspectors verified proper valve lineup for the control rod drive hydraulic units and the removal of fuses to disable the normal drive controls.5.Plant 0 erations.A review was made of recent, plant activities and operations during the period when the fire recovery program was nearing completion and when plans for restart were underway.The review was to determine conformance with the Interim Technical Specifications and commitments in the'Recovery Plan'n the areas selected.The review included examination of the followng, records for the periods indicated:
a.Shift Engineer'.s Journal 6/1-21'/76 b.Assistant Shift Engineer's Journal, Unit 1, 6/1-21/76 c.Assistant'Shift Engineer's Journal, Unit 2, 6/1-21/76 d.'UO Daily Journal, Unit 1, 6/1-23/76 e.UO Daily Journal, Unit 2, 6/1-23/76 f.Surveillance Instruction 2, Unit 2, 5/30-6/24/76 g.Surveillance Instruction 2, Unit 1, 5/30-6/24/76 h.Jumper, Inhibit and Wire Removal Log;outstanding items for=Unit 1, eight and for Unit 2, twenty-five Trouble Reports;about 50 for Unit 2 and 25 for Unit 1 A tour was made was in progress shutdown.Mme standards of an that additional this effort.of'both reactor buildings.where considerable effort to improve housekeeping
'from the long recovery improvement was needed to bring the facility up to operating plant.The plant superintendent stated laborers were being hired to provide assistance in No.inconsistencies with requirements were noted during the review of plant operation ~t'e~IE Rp t.Nos.50-259/76-15 eed 50-260/76-15.IV-1 DETAILS IV Prepared by: G.R.Klingler, Reactor I pector Reactor Projects Section No.1 Reactor Operations and Nuclear Support Branch Date Dates of Inspection:
July 1-5, 1976 Reviewed by: J H.C.Dance, Chief Reactor Prospects Section No.1 Reactor Operations and Nuclear Support Branch 3<'4 Da e 1.Persons Contacted Tennessee Valle Authorit H.J.Green-Plant Superintendent J.G.Dewease-Assistant Plant Superintendent J.J.Erpenbach-Preoperational Test Coordinator 2.Prep erational Retest Procedure Test Results Units 1 and 2 The inspector reviewed the test results of completed preoperational retest procedures.
 
This review'onsisted of verifying the following:
(1)all test changes have been identified and approved, (2)all data has been entered, reviewed and approved, (3)all test defi-ciencies have been identified and satisfactorily resolved, (4).the test met the stated acceptance criteria and (5)the results have been reviewed and accepted by those responsible for test approvals.
 
The followng retest were reviewed: a.b.Ce RG-4, Reactor Safety and Relief Valves, Unit 1 RG-5, Residual Heat Removal System, Unit 1 RG-8, Recirculation System and M-G Sets, Unit 1.d.RG-9, Reactor Manual Control System,:.Unit 1 e.RG-12, Core Spray System, Unit 1 f.RG-21, Reactor Protection System, Unit 1 pl~~
'6'4 IE:Rpt.Nos.50-259/76-15'aad:50-260/76-15 IV-2 ,g..RG-22A, Source Range'Monitoring (SRM)'ystem, Unit 1 h.RG-'22E, Recirculation.
 
Flow Bias System,,Unit 1 RG-.23, Traversing:.Incore Probe System, Unit 1 RG-25A, Process Radiation Monitoring System-Stack Gas Monitoring Subsystem, Unit.1 k.RG-25C, Process Radiation Monitoring System-Liquid Process Radiation Monitoring Subsystem, Unit 1 1.RG-26, Area Radiation Monitoring (ARM)System,'Unit 1 m.n.RG-29D, Rod, Sequence Control System, Unit 1 RG-30, Primary Containment Isolation System, Unit 1 Oe RG-31-.1,.AC'mergency Power System Operation, ECCS Testing on Normal Auxiliary Power and Diesel.Generator Power, Unit 1 pe RT-3, RHR Service Water System, Unit 1.RT-6A, Drywell.Atmospheric Control-Cooling and Ventilation System, Unit 1'Xe'T-6B, Primary Containment Atmosphere Control (Inerting.System)Unit 1 Se u~.RT-14B, Drywell Control Air'System, Unit 1 RT-7, CS&RHR Pump Compartment.Coolers,.Unit 1 RT-15, Offgas System, Unit 1 Ve We RT-22B, Drywell Leak Detection Air Sampling System, Unit 1 RT-22C, A@ca Radiation Monitoring
'System, Air Particulate Monitoring.
 
Subsystem, Unit 1 The inspector identified no deficiencies for those tests reviewe )p lr i)%I 0
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