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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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LUNITED STATESi 4 O
M, ,,pp";- fg - NUCLEAR REGULATORY COMMISSION. M
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I SAFETYEVALUATI'ONBY'THE0FFICEOFlSPECIdLPROJECTS' I W
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SUPPORTING)AMENDMENTNO.61i:TO'FACILITYDOPERATINGLLICENSENO.DPR-77!
<W AND AMENDMENT NO.L5'3H TO FACILITYt0PERATING LICENSE NO.?DPR279) c <
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iTENNESSEE' VALLEY AUTHORITYf' ,
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- SE0VOYAH' NUCLEAR Y PLANT UNITS J 1 AND '2j ' '
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DOCKET N05.:50-327 AND 50-328. -
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1.0 INTRODUCTION
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E if 1 Thissafetyeval'ationaddressesproposedlchangeTVASON-TS-87-29ntobequoyshf['r. I u i Technical Specifications, Units 111 and 2.SSection 3.8.3.2;OThe:changefinvolves: '
'periodic deleting.surveillance and ' adding ;specificf motor-o'perated Jvalves f(MOV)(TOL)!from(those. .",
re testing!of their thermal overload l protective .
devices. In~a: submittal dated May115,11987, su -
June.16,1987, Tennesseef Valley Authorityf(TVA)pplemented by?atsubmittali.~ da proposed: deletion?ofEthree c
categories of MOV and the: addition of one categ'ory toltable' 3;8-2 LofJthel !
Sequoyah Technica1 Specifications; 1Section 3.8.3;2 of the' Technical:Speci-j >4 fications require that TOL'! devices for the;valv_es1specified in?theltable' bei operable, that the operability of thejT0LtdevicelbeMemonstratediperiodically L ,
l and :that the assocSted valve be declared 11noperable:when the?TOL of the! motor?
operator is~ found !to se inoperable. . The individu'altcategoriesi of MOVtaffected t by the proposed Techiiical. Specification change'are?as;follows::
, . . . . , . . r. ...
(1) M0V's'whose TOL device isLto/be permanently bypassed:andithsreforeTto!bei L
deleted from the table (Attachment 1;to 6/16/87l submittal).. ' ' .
-(2) M0V's no longer required.to be activ'e '(to change state.in normalloperationf or during accidents) as a result of changes'in proceduresf orfsystem,~ .. X ,;
configurations ~ arising out of compliance with Appendix;R 'and< therefore' to , q be'deletedifrom, the table' (Attachment 2 to 6/16/87; submittal) " q
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(3) Valves not required to. change 4 tate to prevent or mitigate an accident;; .
J consequently.not required toLb$ tested under ASMELCode Part'1116Section 111 ,
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.andthereforedeletedfromthe. table,(Attachment 3toL6/16/87Jsubmittal)'3 . 0
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- 4) 'Valvss with TOL.devi'ces . required!to be operable andl inadvertently omittedl f rom the techni cal : s peci fi ca tions [( Attachment l 4 ito 6/16/87; submi ttal ) . ~
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2.0 " EVALUATION x 12.1.'M0V's with Bypcssed Overload Devices ~ , d,
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DuringanongoingreviewofelectricaUcalcu1'ations.TVALdiscoveredthatltheJ original voltage drop calculations for Sequoyah's' electrical system-did not' +
' take into; account the voltage drop at motoreoperators caused by the. TOLo . . 4 <
-device in series with the. individual motor.' .When:this?effectlwas:consideredh
'the recalculated motor terminal voltage was. unacceptably low during.certain-transient loading conditions following;an1 accident? To: correct the situation,-
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TVA proposes to bypa'ss. permanently the TOL devices :for the;affected valvesi O
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TVA. notes:as' justification, NRC's Pegulatory Guide 1.106 which'in paraphrase 1 states that (1) TOL during testing.or b). devices should be'either a) continuously bypa to IEEE-279.or (2) TOL devices be set.with 'all uncertainties: resolved in the? '
H direction of ccmpleting the safety? action', 'i' e., set high',L an'd periodica11yi tested. TVA further. states that, given;the high set t point on1the1TOL devices' being bypassed, i.e., locked rotor current, there"isilittle ~ benefit to rein-1, j serting the TOL . devices during valveToperation fo'r testing 7or; maintenance.s ~ l The TOL' device provides two functions:.
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(1) It pr'otects the motor in a lock $dI rotor condition. y >
It may detect by tripping during test progressiveldeterioratio:f of ? 1 (2) the valve.or operator.
TVA has reanalyzed the circuit breakers associated'with the: motors t'o" assure; they will: provide locked rotor. protection 'andlwhere necessary hastreplaced' ..
o breakers; thus TVA' addressed the first function'.' ,TVA:has7 institu utility industry with NRC input to detect deterioration.r [Further, at the next :/ : j~
refueling outage TVA will: implement a= periodic main.tenance' procedure that :
will' measure alltphase currents'of the MOV's during testing.-1This' procedure 1 i'
provides a"second means.'to~ detect defects intmotor operatorior yalve. 'The, combinationoftheseclattertwo; programs; addresses 7the~secondfunction. . .
j A review by the NRC staff and its t.onsultant of these programs supportslTVA's'. ,
a conclusions that the M0V's are adequately protected again.st electrical: fault orLlocked rotor without the'TOL:deviceland that: bypassing of the TottdeviceL ,
will not' degrade system,or plant; safety. Fu rthe r,1the MOVATS ' program' wil la !
provide an' equivalent:and ~withithe'additionLof. periodic phase. current measure-ment ;-ia. superior means of detectingLmechanical'or electrical Degradation 3off "
the motorf operatori or valve.; ;ThereforeW the MOVATF program' provides f aireason-J ,
able justification'for; not removinghthe bypass feature during' periodicLtestingh
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<The possibility lthat the TOL: devices woulidete:tlelectrical' damage during:
. testing:or2 maintenance,Cduringitheidevelopnent~ period:of;thel phase current % _ ,
4 p'g m , . monitoring /resulting in faultKcurrents thatLwould.notttrip;theffeederzbreaker, ~
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Lis[ consideredL too remote to:.requireiremovaliof!the; bypass? , .u v";
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~2.2' M0V's Deleted to Comply with 10 CFR Part 50', Appendix ~R 2
d A total of 10 valves are-deenergized at the' switchboard to conform to: Appendix R; , 'j requirements. The only. time they will normally?be1energizedlis: momentarily l for position indication'.:11f:for any reason the valves are energized for over : -,
- l an hourk a fire watch will. be stationed.
- Therefore, TVA" proposes deleting the '. -
TOL. devices for these; valve operators from theioperabi_lity ~ test;requi.rement.; lThe ' mj NRC staff and its consultant concur.
j 2.3' Valves not Required to! Operate to Mitigate Accident's t >
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Section XI of the ASME Code,.Part III requires: operability testingiof. valves l- required to change position'to mitigate an accident. This. operability testin.g4 '
requirement includes testing'of the TOL'. cA review by.TVA has ide'ntified116 ' , H valves previously included in'this' category that:are actually 'not required l l i
to change position. Eight are safety injection: accumulator valvesLwhich are l required by procedure to be deenergized'at the switchboard!in'anfopen position:
during operation.; Eight more arelvalves in the Essential, Raw' Cooling Water ,
and Component Cooling sptems which do not enange position 1during"thenaccident;. ,,
and'are used to provide flexibility in operation:or maintenance. 'The staff and. g I
its consultant agree that these valves,.not being: required:to: change position 1 in an accident, need not have-an operability test requirement)for. theirc. TOLD devices.;
2.4 ' dditional Valves ,, V d
i TVA has identified 20 additional valves whic.h,'since they'are: required toi 'l
. operate for. accident prevention or'mitigatioce need'to have their'TOL' devices added to the list in the Technical Specificati ws. lThis'is acceptable to NRC 4'I
. staff. <
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3.0 ENVIRONMENTAL CONSIDERATION
Theamendmentsinvolvechangestorequirementswithrespecttoithe[ installation '
-or use of.a facility component-located within'the restricted area a'sLdefined in 10 CFR Part 20 and changes to surveillance l requirements. The-staff has deter ' .
mined that the amendments involve:no significant increaselin the-amounts, and
no significant change in2the types.cof any effluents that may.be: released-
.offsite, and that there is.no significant increase:in individual:or cumulative >
j occupational radiation exposure.gThe Commission has'previouslyl issued'a pro c ji
< posed finding that the' amendments' involve no significant hazards consideration
.and there has been no:public" comment on such finding. :Accordingly, the: amend ' ,
i
'ments meet the eligibility criteria for categorical exclusion set forthlint10; E
CFR 51.22(c)(9). ePursuant!to~10 CFR 51.22(b). no" environmental' impact;statei '
9 ment not environmental. assessment need be' preparedtinfconnection'with!thc;
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issuance of'the. amendments.- -
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- 4.0' CONCLUSION- ,
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- Based on reviews by the staff. and its consultants, the . staff'concurslin ' he1 t
deletions and additions to1 Table 3.8-2 of the-Technical Specifications, Thel NRC staff notes TVA's commitment toLimplement a M0 VATS program priorJto .
restart of unit 2 and implement phase current monitoring of:all MOV's:(both those covered by the EQ program-and those not covered) during the next : C refueling outage of Unit 2 and. prior to' restart ofsunit 1.-
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JWe have concluded, based on the' considerations discussed.above, that: L(1).there l is' reasonable assurance that the health and safety of"the:public will.not be i endangered by operation in the proposed manner, and-(2) such" activities lwill. 1 be conducted in. compliance'with the Commission's regulations..and theLissuance H of the amendments will not be inimical to the 'conson' defense and security nor to 'j the health and safety of the public.' j l
l Principal Contributor: Edward-F. Goodwin, Thomas'SE Rotella j O
l Dated: 0ctober 22,'1987 q
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