|
|
Line 77: |
Line 77: |
| irproved by TVA's corrective actions and the concern with program inadequacy was no longer valid. l | | irproved by TVA's corrective actions and the concern with program inadequacy was no longer valid. l |
| ' TVA provided a final report nn the Unit TVA's 1 IE Bulletin 79-14identified final report program to thea that ; | | ' TVA provided a final report nn the Unit TVA's 1 IE Bulletin 79-14identified final report program to thea that ; |
| 4 hRC in a letter dated August 4, 1988. ! | | 4 hRC in a {{letter dated|date=August 4, 1988|text=letter dated August 4, 1988}}. ! |
| corprehensive orogram to review rigorously analyzed piping and generate suppnrt i calculations had been performed. This program included additional inspections These i of piping and si ports to Special Maintenance Instruction SMI 0-317 69.The staff ; | | corprehensive orogram to review rigorously analyzed piping and generate suppnrt i calculations had been performed. This program included additional inspections These i of piping and si ports to Special Maintenance Instruction SMI 0-317 69.The staff ; |
| inspectiers were performed after the ECTG report had been coroleted. l review of tre Unit 1 IE Bul'atin 79-14 program concluded the program was adequate ! | | inspectiers were performed after the ECTG report had been coroleted. l review of tre Unit 1 IE Bul'atin 79-14 program concluded the program was adequate ! |
|
---|
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 ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively 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 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 ML20057D5321993-09-28028 September 1993 SER Granting Licensee 921117 Relief Requests ISPT-2 & ISPT-3 Re Inservice Pressure Test Program 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) 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 ML20206G4531988-11-0404 November 1988 SER Supporting Employee Concern Element Rept Co 15101, Floor Drains ML20206G3961988-11-0404 November 1988 SER Supporting Util Investigation of Employee Concerns as Described in Element Rept 308.03 ML20206G5341988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 30114, Malfunction of Doors ML20206G4621988-11-0404 November 1988 SER Supporting Employee Concern Element Rept 204.8(B), Communication & Interface Control 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 ML20206G4571988-11-0404 November 1988 SER Supporting Employee Concern Element Rept Co 15105-SQN, Flex Hose Connections ML20206G4971988-11-0404 November 1988 SER Supporting Employee Concern Element Rept 23501, 480 Volt Power Receptacles Unsafe ML20206G4861988-11-0404 November 1988 SER Supporting Employee Concern Element Rept EN 232.9(B), Freezing of Condensate Lines ML20206G4591988-11-0404 November 1988 SER Supporting Employee Concern Element Rept 204.7(B), Vendor Documents Legibility & Dissemination Sys ML20206G4801988-11-0404 November 1988 SER Supporting Element Rept EN 232.2, Carbon Steel Vs Stainless Steel Drain Pipes ML20206G4721988-11-0404 November 1988 SER Supporting Employee Concern Element Rept 22912, Panel- to-Equipment Distances ML20206G4661988-11-0404 November 1988 SER Supporting Employee Concern Element Rept EN 229.6(B), Lack of Valves in Sampling & Water Quality Sys 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 ML20206G3661988-11-0404 November 1988 SER Supporting Employee Concern Element Rept EN 21002, Inadequate Environ Qualification of Electrical & Instrumentation Control 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] |
Text
. .
- y s' * % % UNITED STATES
!y. l1 NUCLEAR REGULATORY COMMISSION
- . .. e W ASHINGTON, D. C. 20555 WW'.! .
l SAFETYEVALLATIONR;.PCRTBYTHEOFFICEOFSPECIALPROJEC'1 ELEMENT REPOPT 212.2(B) REVISION 1 PIPE SUPPOPT PROGRE l
[
NRC BULLETIN 79-14 ABR PROGRAM f
TENNESSEE VALLEY AUTHORITY :
i SEQUC)AH NUCLEAR PCWER PLANTS UNITS 1 AND 2 ,
DOCKET N05.: 50-527 AND 50-328
- 1. SUS.'E CT Category: Engineering (20000)
Subcategory: Fipe Support Program (21200)
F.lement: NRC Bulletin 79-14 AER Frogram (21f:02)
Conceens: IN-85 027-001, SQN-86-002-02 The basis for Elerent Report 212.2(E), Revision 1 are the following employee cencerns which question the adequacy of piping analysis oesign documente. tion
! at TVA plants:
i '
IN-85-027-001:
l
'VA Program for implementing hRC Bulletin 79-14 inadOquate. Design calculation documentation is lacking, ,
SZ 85-002-OLJ [
During the exit interview the Ci stated that containment spray line drawings and weld map do not agree with as butits. Alternate analysis
' was used instead of rigorous analysis, drawing.) were not corrected. {
l 11. Surr.ary of Issues The Erployee Concerns Task Group (ECTG) report identified the following four ,
issues from the employee concerns:
- c. TVA program for impleeenting NRC IE Bulletin 79 14 is inadequate. ,
- b. Nsign calculations that address the resolution of 79-14 program (
discretancies lack proper decurentation, j t
+
ca112202,"$ $$ N;327 !
ppg ADC PDC P I
._m . . =_ _
l
! c. Centainment spray piping does not reflect "as-constructed"- '
configuration in terms of routing as well as weld locations. :
l
- d. Containrent spray piping was analyzed using Alternate Analysis k rethod instead of Rigorous Analysis method, III. EVALUATION I To address issues a and b. Element Re,~rt 212.2(B), Revisien 1 provided a ;
chronology of TVA's actions in response tc IE Bulletin 79-14 for bothThe e !
Sequoyah Unit 1 and Unit 2.for the initial Unit 1 IE Bulletin 79-14 program and it wa ;
Urit 2 program. The element repnrt also found that the concern with lack of i
- umentation, issue b, was not valid for both units. The NRC staff had '
previously reviewed TVA's implementation of IE Bulletin 79-14 and However, the closed staff the l i
bulletin for Unit 2 in Inspection Report 50-3?a'11-42. [
1 had rot closed the bulletin fer Unit 1, !
l ,
i Curing its review of civil calculations TVA determined that a large number TVA of 4
rigotously analyzed pf pe support calculations were not retrievable. ,
initiated a program to regenerate these calculations. As part The of this staff program, evaluation ;
l TVA performed additional inspections of pipe supports. Based on j
of this progra* is contained in Section 2.3.2 of NUREG-1232. Volume 2. !
the results of this program the staff considers the concern raised in issue b [
valid. Based on the staff's review of TVA's corrective actions in Inspection the staff corcluded that the issue had been adequately !
j Report 50-327, 328/88-12 l
- addressed for Unit 2 restart.
1 Element Report 212.2(B) contained a discussion of TVA's corrective actions for l deficiencies program.
that had beer identified in the Sequoyah Unit 1 IEj !
j Maintenance it.struction SMI-1-317-24 to correct the identified deficiencies The element report concluded that the Unit 1 program had been substantially
{
irproved by TVA's corrective actions and the concern with program inadequacy was no longer valid. l
' TVA provided a final report nn the Unit TVA's 1 IE Bulletin 79-14identified final report program to thea that ;
4 hRC in a letter dated August 4, 1988. !
corprehensive orogram to review rigorously analyzed piping and generate suppnrt i calculations had been performed. This program included additional inspections These i of piping and si ports to Special Maintenance Instruction SMI 0-317 69.The staff ;
inspectiers were performed after the ECTG report had been coroleted. l review of tre Unit 1 IE Bul'atin 79-14 program concluded the program was adequate !
to verify the as built piping configuration. The staff evaluation of the Unit 1 l
I r program is the subject of a separate safety evaludtion on Part 2 of the Sequoya[
Nuclear Performance Plan. '
t To address issue c, Ele-ent b rort 212.2(B) provided the results of a review isc~etrics with the !
I which cc~ 3 red ter as-Constructed Contain*ert soray pipingBased on its ;
desigr- calculattens. the as-Constructed oipirg configuration #or the contain-reaso'1aM e tc'irranet ,
nent spray syste*. 49 tees with the as-designed configuration, and that field i
F
- Subsequent welds are apprepriately shown in the as-constructed drawings.
to the ECTG review, the Unit 1 containment spray system received additional as-built review during the S.w!-0-317-69 inspections. The as-built configu. .
ratien of piping supports on the containment spray system also received '
additional review during the staff's Safety System Ouality Evaluation.
Based on the ECTG review, subsequent TVA
'. Inspection Reenrt 50-327, 328/83-29. j inspections and the staff's Safety System ',uality Evaluat W. inspectier., the I staf f conddes that the concern with adequacy of the as-built configuration of '
containment : ray system has been adequately addressed for restart.
To address issue d. Element Report 212 2(B) provided the results of a The review ECTG of TVA's use of alternate analysis on the containment spray system.
report concluded that the criteria for using alternate analysis had been ret 7 Concerns with 1"A's use of alternate analysis :
and the :ncern was not valid. l had also been the sut. ject of a separate evalue son in Element Report 218.4(B),
Revision 2. In addition, as a result of deficiencies that had been identified 4
with Iternate a..alysis piping designs and design documentation, TVA initiated i
' an alternate analysis program. The staff's evaluation of TVA's alternate Based on i analysis program is :entained in Sectien 2.4 of NUREG-1232, Vol. 2.
i the ECTG review and the staff's review of the implementation of the alternate ,
analysis program, the staff cencludes that issue of.TVA's use of alternate ,
' analysis for the containrent spray piping has been adequately ad.'tssed fer [
restart.
TVA will perform artditional reviews of alternately analyzed piping in its Phase !!, post-restar'.. program. l IV. Conclusions c Based on the review of Erployee Concerns Eienert Report 212.2(B), Revision 1; f l
l the NRC's inspections of TVA's IE Bulletin 79-14 program; TVA's additional as-built reviews for Unit 1; and the staff review of the alternate analysis program, the sta'f concludes that Empicyee Concerns IN-85 027-001 and :
1
- SON-86 002-02 have been adequately addressed at Sequoyah for restart. r i
l [
f i !
- [
i l
- i i !
i
- - - _ .