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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
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l l
/p' %9'c UNITED STATES l'
!\ .. g ,
- NUCLEAR REGULATORY COMMISSION i
$ I .- M'5 W ASHINGTON. D. C. 20688 Yff StJE'Y EV LUATION REPORT Fv TPE1OFFi E OF SPECIAL PP0JECTS EypLnVEE CetCERN ELEvENT REDORT OP 30501, "ACCESS!RILITY PROBLEWS"
! TENNESSEE VALLEY AUTHORITY ;
SEOUOYAu NurLEAR 90'4ER PLANT llNITS 1 A 7 l t
I DOCKET N05. 90 3?7 AND 50-328 I. Sutje:t 4
Catege y: C;e-ati:ns (30000) !
- S;:: ate;: y: 1::essibility (30500)
! Ele en.: A::e s sidi11ty Pr:51 ems (30501) ,
l In : asis fer Ele eet Re: rt CP 30501-SQN, Rev. 4, dated March 12, 1957, }
l are the foll w ; e pic>ee cen: erns: i 1 Cenetr. IN 525-159-C01 WE'io Unit 2, ence scaffolding is re eved, scee !
i valves would be hard to get to, e.g. , 15 feet !
I eff fleer, to manually open or clese valve. i
! CI :culd not provide specific valve rumbe*s, l i systems, buildings or elevations. CI stated this {
i c 9ditiori exists throsghout the plant. -
i
- 0: :e n IN-55-IS?-002 Valves lo:ated in WE'.P Unit 2 South Valve Roem l
- are sery cengested and ina
- :essible. Only a j 1 s all person weald be able to get to them. CI l stated one example is Orain Valve on Main Steam l
System in South valve R::m Unit 2. CI could not i provide any additional details, i
- i
' Cen:ern I'-55-3CE-001 Varicus equipment that could be needed during an l emergency is net readily accessible to applicsble L pers:nnel. Example: Auxiliary Bufiding 713' Elev (also Contain ent Building) the instrument l
- ranels and the auxiliary feecvater pu ps art se j 1 congested it is very time consuming to get in >
l t*ere to read the instruments. Nuclear Power !
l C:n:ere. Cl has no further inferratien. I 1 t I
i C:*:e-r Pi-55-C03-0C6 Watts Bar Instrutentation is not properly i cesi;aed for a::essibility. CI tas ro re-e t f
a::iticnal information availaole. , },
l C: :e-r :'-55-22C-0C1 Le t: en:essive re-te- cf hangers a': i
- :.e : :.: ; n L-t 2 Rea:t:r E.41: c;. t j +::i: : .. 1::. .'at:- -::- n.-:n- *
, -ea'.' l
- mns) c.
' ,5 :s ;m e s ( . ; : aM
. G811220312 881104 c:eraticns are anti f: Ated. Cl f eel s tra*. P:t t
, PDR ADOCK 05000327 ,
i P PDC ea: ;n ::a:ern was sr:an regar:ing tre nWT:er Cf l haagers teing used. COnstru tion cepart*ent l f
2 concern. CI could not provide any additional details / specifics.
Con:ern IN-55-617-001 The building of hangers & pipe support systems to the point of accessibility being made impossible.
This concern involves eoth units 1 & 2. The primary places of interest are: roof, Auxiliary Building elevation 737, the ERCW vent valves, CCS ,
valves to heat exchangers, number 4 accumulator room, north & south steam valve rooms & elevation 713, boron injection tank (BIT) room. Accessi-bility is nonexistent due to potentially hot pices & congested areas. Presently there are scaffolds to some inaccessible a r e a *. , when scaf folds are removed, no access will be avoil-aule.
C:r.;e-n RII-56-A-0116 The alleger stated that at Watts Bar and
- ec; > ah, control parels or stations are chysi-cally located such that there is no way to get to the- to crerate the emergency equipment. As an example, a panel was observed to be located six to eight inches from a wall, facing the wall, so that tnere was no physical way to even r sad ,
the tags 09 the panel. The alleger said that there were a "lot" of ankwardly located panels a',
Watts Bar. 9 N:te: 5;N elevati:ns are 23 feet telow tr:se a,t kBN. SQN main stcam valve ro: s are situated east and west.
Tne first six e cloyee concerns listed above were specific to Watts Bar N;;1eae Plant 'hBN), but eval;Ated oy TVA as generically applicable to 5;N. Tre severth employee concern was specific to Coth WBN and SON. Feur
- f the sesen employee ccccerns were evaluated by TVA as nuclear safety t relatet.
II. 5;.--ary of Issue i i
- 1. Concern IN 55-159-C01. Val <es recuiring manual operatien woul: te (
cifficult to access if scaffolding isn't installed. i
- 2. Ccreern ;N-i5-159-002. Valves ic:ated in SON east and west valve c::ms are c:rgeste: and inaccessible, f
- 3. C: :e n !N-56-3 6-:01 Ecui: ent reece: curing an e ergency is ,
c4'ficult to access for applicaole person e1. j
. C:a:e - :--55-::3-026, lastr. entatier is c:t ces4;ae f:r r
-:- f.- .,e : :.: ; :.e :: e.:ess4,e a ;e- ;
i*stallati0a ir t*e ria*t0r OJil0ir; may ca .se ALARA : n:er*s caria.g ,
p' ant C;e'aticas.
1
- 3
- 6. C:n:ern IN-85-617-001. A:cessibility to equipment has t;een made !
) alm:st impossible in several plant areas at SQN due to installation
- of hanger and pipe support systemt.
- 7. Cen:ern RII A-0116. The physical location of control panels and stati:ns at SCN prevent, in seme cases, personnel access for :
c;erati:n in e ergen:y situations.
!!! Evaluati:n ,
Because cf the conspe:ific nature of the first six employee concerns and l their relative similarity, TVA addressed these by evaluating: (1) the i progra at SON for icentifying and ccerecting access problems, and (2) access pr:blems in plant locations specifically referenced in the state ents cf the employee concerns.
- TVa perfer e a spe
- ific evaluation of employee concern R11-86-A-0116 :
tecause it was ad:ed to the ele ent report af ter the original six con: erns ;
aert initially evaluated.
TVA terfor e: walkde.ns to evaluate the accessibility of equipeent for ,
c:e-ati:n (caring nor al, off-normal, and emergency conditions),
maintenance, and testing in plant locations specifically addressed in the su Je:t e pl yee cen: erns. The persent el sefety aspect of equip ent l i a::ess was also evaluated. Control stations and components requiring j 1e:al ::eratien under other than normal conditions were identified the '
malideon progra . by revie,< of SQN emergency iastructions (Els), abnormal irsteu:t ers (ACIs), and function restoration guidelines (FRs).
i
- eratir; I
TVA also to:( crecit fer the ECP Validation and Verification program cercu:te: at SON in March 1956 in their evaluation of the accessibility of I e ergea:y equip ent requiring local operation. !
Irterdeas with SCN eperators were conducted to identify any pecblems with L I access to local control stations for emergency equipment. l>
1 [
IVA c:a:1ude: that a::ess to certain areas is a pr0blem at SON; therefore, l
( ea:n of the e ployee cencerns is valid to some extent, However, emergency f e:vir eat is accessible and acequate, and proper enintenance can t:e (
a::: olisee:. SON is sensitive to snis issue as illustrated by past, as j well as engeirg, icentification and correcticn of a: cess proclems. ;
Alt m ;h the current program is less cefined than in the past, it appears ;
to be effectise in identifying and correcting access problems. No i safety-related ceficieacies were identified by TVA in this evaluation.
(<
'. V . - .' siar C0a:
p t
1 The MC staff telieves tnat tne TVA investigatten of the ::r:ern was ace:Jite, arO t*eir resclution of the concern as descrited in Ele ent
'e::rt C; 20E01 is a:*ertatle f 0r restart. I I
4 F
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