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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20239A0631998-08-27027 August 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2 ML20236Y2091998-08-0707 August 1998 Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08 ML20217K4471998-04-27027 April 1998 Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05 ML20138D2581997-04-28028 April 1997 Safety Evaluation Authorizing Licensee Proposed Alternative to Use 1989 Edition of ASME Boiler & Pressure Vessel Code, Section XI for Performance of Containment Repair & Replacement Activities Until 970909 ML20057F8441993-10-14014 October 1993 SER Granting Relief Giving Due Consideration to Burden Upon Licensee That Could Result If Requirements Imposed on Facility ML20057D6351993-09-28028 September 1993 SER Granting Relief as Requested for Both ISPT-2 & ISPT-3 Per 10CFR50.55a(a)(3)(i) & 10CFR50.55a(g)(6)(i) ML20057D5321993-09-28028 September 1993 SER Granting Licensee 921117 Relief Requests ISPT-2 & ISPT-3 Re Inservice Pressure Test Program ML20128K0221993-02-11011 February 1993 SE Accepting Util Justification for Break Exclusion of Main Steam Lines in Valve Vaults Provisionally Until End of Refueling Outages ML20128E9161993-01-0606 January 1993 SE Approving Request for Relief from ASME Requirements Re First 10-yr Interval ISI Plan ML20247K3321989-09-14014 September 1989 Safety Evaluation Accepting ATWS Mitigation Sys,Pending Tech Spec Issue Resolution ML20245E6951989-08-0303 August 1989 Safety Evaluation Supporting Inclusion of Alternate Repair Method to Detect microbiologically-induced Corrosion in Previously Granted Request for Relief from ASME Section XI Code Repair Requirements ML20247G8661989-07-21021 July 1989 Safety Evaluation Re Silicone Rubber Insulated Cables. Anaconda & Rockbestos Cables at Plant Environmentally Qualified for Intended Function at Plant & Use Acceptable for 40 Yrs ML20247B4891989-07-19019 July 1989 Safety Evaluation Supporting Util 890330 Request to Eliminate Dynamic Effects of Postulated Primary Loop Pipe Ruptures from Design Basis of Plant,Using leak-before- Break Technology as Permitted by Revised GDC 4 ML20246N0321989-07-11011 July 1989 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 1.2, Post-Trip Review,Data & Info Capability ML20244D1771989-06-0909 June 1989 Safety Evaluation Re Generic Ltr 83-28,Items 2.1.1 & 2.1.2 NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley1989-05-26026 May 1989 Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley ML20245A1301989-04-14014 April 1989 Safety Evaluation Re Shutdown Margin.Procedural,Hardware & Training Enhancements Implemented & Committed to by Util Will Provide Reasonable Assurance That Adequate Shutdown Margin Will Be Maintained at Plant ML20244D8821989-03-14014 March 1989 Safety Evaluation Supporting Procedural,Hardware & Training Enhancements Implemented & Committed to by Util to Provide Reasonable Assurance That Adequate Shutdown Margin Will Be Maintained at Plants ML20195J0891988-11-28028 November 1988 Safety Evaluation Accepting Program for Plant in Response to Items 4.2.1 & 4.2.2 of Generic Ltr 83-28 Re Reactor Trip Sys Reliability ML20205T1621988-11-0707 November 1988 Safety Evaluation Supporting Improvement Plan for Emergency Diesel Generators Transient Voltage Response ML20206G5341988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 30114, Malfunction of Doors ML20206G4971988-11-0404 November 1988 SER Supporting Employee Concern Element Rept 23501, 480 Volt Power Receptacles Unsafe ML20206G3961988-11-0404 November 1988 SER Supporting Util Investigation of Employee Concerns as Described in Element Rept 308.03 ML20206G4571988-11-0404 November 1988 SER Supporting Employee Concern Element Rept Co 15105-SQN, Flex Hose Connections ML20206G4591988-11-0404 November 1988 SER Supporting Employee Concern Element Rept 204.7(B), Vendor Documents Legibility & Dissemination Sys ML20206G4621988-11-0404 November 1988 SER Supporting Employee Concern Element Rept 204.8(B), Communication & Interface Control ML20206G4661988-11-0404 November 1988 SER Supporting Employee Concern Element Rept EN 229.6(B), Lack of Valves in Sampling & Water Quality Sys ML20206G4721988-11-0404 November 1988 SER Supporting Employee Concern Element Rept 22912, Panel- to-Equipment Distances ML20206G4801988-11-0404 November 1988 SER Supporting Element Rept EN 232.2, Carbon Steel Vs Stainless Steel Drain Pipes ML20206G4531988-11-0404 November 1988 SER Supporting Employee Concern Element Rept Co 15101, Floor Drains ML20206G5291988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 301112, Sys 31 Not Operated Properly ML20206G5241988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 30111, Valve Closure ML20206G5191988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 30105, Questionable Design & Const Practices ML20206G5091988-11-0404 November 1988 SER Supporting Employee Concern Element Rept 23706, Gassing of Current Transformers ML20206G5021988-11-0404 November 1988 SER Supporting Employee Concern Element Rept 23504, Exposed HV Cable Routed W/O Raceway - Personnel Hazard ML20206G4861988-11-0404 November 1988 SER Supporting Employee Concern Element Rept EN 232.9(B), Freezing of Condensate Lines ML20206G5391988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 30204, Ground Detector Problem ML20206G5431988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 30301, Difficulty in Obtaining Obsolete Equipment ML20206G6111988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 31105, Alara ML20206G6161988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 31106, Health Physics Facilities,Clothing & Protective Equipment ML20206G6211988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 31204-SQN, Mgt & Personnel Issues ML20206G6321988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 31208-SQN, Security at Plant Entrances ML20206G6371988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 31201-SQN, Adequacy of Public Safety Svc (Pss) Officer Uniforms in Nuclear Plant Environ ML20206G4351988-11-0404 November 1988 SER Supporting Employee Concern Element Rept Co 11101-SQN, Contact Between Dissimilar Metals ML20206G4381988-11-0404 November 1988 SER Supporting Employee Concern Element Rept Co 11202-SQN, Craft-Designed Hangers as Related to Const ML20206G4081988-11-0404 November 1988 SER Supporting Employee Concern Element Rept Co 10307-SQN, Uncoated Welds as Related to Const 1999-09-23
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20217G3721999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With ML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20210G6631999-07-28028 July 1999 Cycle 9 90-Day ISI Summary Rept ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209H3831999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20195K2951999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20206Q8951999-05-0505 May 1999 Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10 ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20204C3111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20203H7381999-02-18018 February 1999 Safety Evaluation of Topical Rept BAW-2328, Blended U Lead Test Assembly Design Rept. Rept Acceptable Subj to Listed Conditions ML20211A2021999-01-31031 January 1999 Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199G3641998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20197J5621998-12-0303 December 1998 Unit 1 Cycle 9 90-Day ISI Summary Rept ML20197K1161998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20195F8061998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Sequoyah Nuclear Plant.With ML20154H6091998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20154H6251998-09-17017 September 1998 Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 Colr ML20153B0881998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Sequoyah Nuclear Plant.With ML20239A0631998-08-27027 August 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2 ML20236Y2091998-08-0707 August 1998 Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08 ML20237B5221998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Snp ML20237A4411998-07-31031 July 1998 Blended Uranium Lead Test Assembly Design Rept ML20236P6441998-07-10010 July 1998 LER 98-S01-00:on 980610,failure of Safeguard Sys Occurred for Which Compensatory Measures Were Not Satisfied within Required Time Period.Caused by Inadequate Security Procedure.Licensee Revised Procedure MI-134 ML20236R0051998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Sequoyah Nuclear Plant ML20249A8981998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Sequoyah Nuclear Plant,Units 1 & 2 ML20247L5141998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Sequoyah Nuclear Plant ML20217K4471998-04-27027 April 1998 Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05 ML20217E2221998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sequoyah Nuclear Plant ML20248L2611998-02-28028 February 1998 Monthly Operating Repts for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20202J7911998-01-31031 January 1998 Monthly Operating Repts for Jan 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 ML20199F8531998-01-13013 January 1998 ASME Section XI Inservice Insp Summary Rept for Snp Unit 2 Refueling Outage Cycle 8 ML20199A2931997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20198M1481997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20197J1011997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199C2951997-11-13013 November 1997 LER 97-S01-00:on 971017,vandalism of Electrical Cables Was Observed.Caused by Vandalism.Repaired Damaged Cables, Interviewed Personnel Having Potential for Being in Area at Time Damage Occurred & Walkdowns ML20199C7201997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Sequoyah Nuclear Plant L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation 1999-09-30
[Table view] |
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/p 9'c, UNITED STATES i j !N NUCLEAR REGULATORY COMMISSION !
3 .\, , ~3,!I wAsoctoN. o. c. aosss !
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SAFETY EVALUATION REPODT BY THE OFFICE OF SFECIAL PROJECTS t J
EwPLOYEE CONCE:N ELE *ENT REPORT OP 30P01, ADE00ACY OF PROCEDURES" !
- 1 TENNESSEE VALLEY AUTHORITY I
SE000 YAW NUCLEAD POWER PLANT UNITS 1 & 2 t
00CVET NOS. 50-327 AND 50-328
' I I 1. Subject l r
- Cate
- ery: Operations (30000) l Subcategory: Maintenance (30800)
Ele ert; Adequacy of Procedures (30801) i i
6 I
Tre basis f:r Ele eat Re;;rt 30501, dated March 16, 1987, are the [
j fel10 ir; em:1 yee :: : erns: l i
' C:r:ern w ,-55-004: A:e:va:y of Mi-10.43
! Cen:ern WAS-56-001: Ade:va:y of MI-6.20 1
C:Pr.een Ta';-55 C;2: M91-9 coes n:t s;ectfy t: :.e f:r screws less than l
40.
1 i Cen:ern TAs-55-004: Lucricatten Of geared lintt switches en MOVs not i i pr:;erly inspected.
t i
! C: :ere 50 -ii-0C9-004: Mainte-aece instev:ti:as a*e vn: lear and de ret I crevide a:e:vate instra:tien. Cetails kne.n to l QTC, withheld due *o .
c:nficentiality. No +
l i
further information may te released. Nuclear I 1
Fe.er de: art ert concern.
1 l C:n:ern SQP-S6-014-001: Feceman :: ret always su:p:rt the craft in '
providing the'n with eve *ytning tney Peed to CO the j:b. e.g.. require 0 : Pints. Nu*Iear EC.er l
i ::n*ern. Cl Fas PC fur *"er inf:r*atien.
i
!!, Sv**ary a' !ss.e A. {0*:ern MAS-ii-204 westi:ne 15e ade:ua y O' MI-10.43, Relve i:atten f V** *s. I* i s *a * *te a s *
- e i r str. ti 0n a *resse gereci*aII)i **e -
'. ' !
- t * : t ;'s . * * * . ' * ; ; e ' t a a: e , al *
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l; : e e s- ' s. : .est *; :.se.
j mso316 es1104 7
, 'kDOCK 0500 I
i P
o 2
1
- 5. Con:ern .YAS-56-031 vestioned the ade:uacy of MI 6.20, Conf t;ura: ten Control 0 ing va intenan:e A:tivities. inis raintenance instru:ti:n addressed .he subje:t of configuration ::ntrol caring the ainte a :e tr:utleshooting pro:ess via a data package cover sheet an ::.ff;u-rati:n :na ;e cata sneet.
C. Oca:ern TAK-55-002 questioned the adecua:/ of M&Al-9 te:ause it ei cet s:e:ify t:rcue values for s:rews less than slo. P!.AI-9, Ti;ntening, Ins:e:: ion, an: 00:u entation of Bolted Connections, is the ::;nt: ant ::sfi:aticns and a:ditions instruction.
- 3. ::r:ern TAN-55-C04 cuestioned the ade:vacy of the irsce:tice/
'.. 1:stien of ge:re: li.it s it:nes on MOVs. MI-10.46, t.imito ;ue V:::e C: erat:rt; ntrol Vs15e is the tegnizant mainteaance instr.*ti:n.
C. 0:n=ern 500-56-009-004 cuestioned the adecuacy/:larity of raintena*:e instru::1: .s in ;ereral. Tnere are 213 maintenan:e innru::icns liste: in :e Se:w:>an maintenan:e instru:tions index. 5 0 v.- 1, Se: :>aa N.: lea
. :taa Yaintenar:e Feogram, provides tre stancard
- a:tice f:r writte- aintenan:e instru::1:ns (MI) in paragraph 5.0.
. C: :e n 50?-5f-0;;-031 Ouestiened the ::rpleteness of the work l :a:.a;e tan : e a:ete*s get frem tee foreman (ard plan ers) -
! see:iti:ai'y :e re: wired :*ints. 50Y-2, Maintenan:e Ma age ent Sy s
- e"' 0 3 r t r a i s t*e w:"A re:Wes*/=:rk pa:kage pr: ess at Se:a:yan.
... . . 5 ' . ., . o . .
- a. vis-i5-:::: v:-;0.15 mas eee e:la:e :. MI 4 5.2.1 f or ;elia :e v:t:rs, M:-15.4.1 f:r A1115-Chairers/5 e e e illis motors, and v:- 5.6.1 f or Westingacuse ret:rs. This :ro:edure replacem nt nas snif e: e latri:sti:n of rot:rs fr:9 a :iant generi: a: preach to a i
s:e:i'i; wea::r a::rea:h.
1 8 5. vi5-Ei-:01: N* Se:ti:n 5.4.2.2 ceft es t*e re:vice-erts f:e
- te
- : a y alte-ati:ns ra:e to :lart e:vi: ent during tre :lesn::ti q .
- N:: 55-017, ::r:u:t of C:eratices, Chapter 13, C: rte 1 of Te :o se>
v::3 #':::':n :r:,' des ;u':elices for -:.cles ::tia;. VI-i.00, iev. !C =ates C::::er 10, 1956, reets ::n : e require ests :f tre NOAY and tre gui:elines of IN:0 55-017. he NRC has :erfer e: a revie. Of tre N;AM a;ainst 10 CFR 50 A::e-:ix B am 1:eetifie: n:
cis~re:a :ies.
- . *: :::: v ',1 : - 9 was :0 pletely re r': ten in Ce:e :er 'di5 :
re#'s:: *e ea ele::*4:31 tor:uiag 1-0 ::ited ::~e:ti:as
'e:.i'e e'*.s in t"e realy revised G-35 ste:i'i:stices. Se:ti:n 3.5 ~
- 3*35 sta*.es **at ::reas si:e s;0 ce $ 3er, used iP *a 'e s:Ii;es 10 te**'*a*.' *5 5'a Oe t';*te*e 10 *e ::'*t 3: a*'** t~e ' :=
-15 r it: 4: ,
- .'*; .a'.ai !-e ; .+" *;* i
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3
- 0. TAK-55-004: MI-10.46, steps 6.1.4 through 6.1.7 provices f:r tre l lutrication of the geared limit switches and also penvides for C; !
hold / ins;ection ::ints. t.imitorque corporatten as well as Se:a:yah l Nuclear Plant has experienced grease hardening pr:blW95 in hi;n ;
te :erature en.te:n ents with the lubri: ant (Beacon 325) origieally ;
furniste: in ; eared limit saitches. TVA initiated a WMR t: ::nwer the grease in the geared limit s itches of all limitercue operators L t: F0311e Grease 23 ahich was recer-ended by limiter;ue. This l re: wire: restart item is a1rost co plete at Sequoyah, [
t E. $0:-56-CC9-004: ine TVA hv;G perferred a revte of eatntenan:e at !
E* s Cerry, Se:. yah, a: Watts Bar duricq the spring and su- er cf 1936. ?i V RO fia:ing #E*2 states "$ *e instructions were n0t Clea*. !
-ere a:t :Or:ise, anc cid not contain the infor.tatien ne:essary for esers :: . Oerstae: a-d perfor w:rk activities effe:tively"; it e- l
- evice
- fcur eaa-;les see:ific to Sequoyah. The Manager of Nw: lear r F:.ee :rev':ed t,nis hvRG re: ort to his operattens staf f ard aske: f:r !
cerre:,ive a : t i e r. :lans ey Nose-ter 1956. Tne Sequeyan Nuclear l Terf -a :e :ia (revise ) 4:kne. ledges the co-mitrent to enna :e M s :
(see ra;es : -3 at: -59). Fai .tenance manage ent at Seau:yah nas
- e.ei::e: a :r:;-a- f:e M1 enman:e ent, which completes the e- a :e e ; :r:g a* in t o chases: a higher risk cate; ry in 8 L
-:-tas a-: a 1:aer ri s( cate;:ry in 21 nontns (after startue). This s: e:.'e is tei ; tra:(e: en MATS (TVA's canagement actien tra: ting l syste-).
I F. 5;D-56-J14-C01. Se:w yah utili:es forter --aft personnel as ;1aree-s (
- : t a' :. t e -: i +: vested by tre A: vR :r::ess, including ; e l 3 ..e s: :f t e -:-( a:*a;e. The olanre cly inclu:es tre re:vice:
- a ie;5 '- e .:rk :a:kage wren he s ws the9 up to previce l irstra:ti: s for ; at ea:ia;e %:r al'y the planner will enly ;
- wice t~e : a 4 ; ru-:er either in the -:rk pa:Lage er in the wors ;
'astra:ti:rs. S e for ~an aa: res; nsible :raftman sign the Instra:- .
ti:e ;eview sneet verifyi g that t*e testry:tions inclu:e are j a:e:. ate f:- :ee': -ir; tre :rk. The i-:1asien of tne re:essary
- i ts in tre *:ri :a:Aa;e is e: at:resse: in 5 3-2. TVA feels trat
- e
- !aerers a e ;revici g tne c:rrect, raterial fer the crafts en to ;
- e ': - tne .4: . 5:ecifically, in tae :ase cf drawings, eit*er t*e (
- e e: :ca.ir; :- t e Ora.i ;r.-:er is s.:: lie:. ;
L IV. C:aciusten ;
r Tae ',R- staff te' e.es st : e TVA 4*sestigaven :( the ser:ee s was i a:e:. ate, a-: t ei es:'.t':- f t e :: : eras as :es:*.te: t- Ele e-- I
- e
- : t :: :O :'. 's a::e:ta: 1e f:r restart. j l
I l
r i
L l
h
_ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _