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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 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
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SAFETY EVALVATION REPORT BY THE OFFICE OF SPE', At PROJECTS EMPLUYEE CONCERN ELEMENT REPORT OP 30105, "OUESTIONABLE DESIGN AND CONSTRUCT!ON PRACTICES" TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR POWER PLANT UNITS 1 & 2 DOCKET NOS. 50-327 AND 50-328 l I. Sub!e:t I Cate;:ry: Cperations (30000) I l
t Sub:stegory: Mechanical Ecut; ment Reitability/ Design (30100) l Eleme-t- Quest.':nable Design and ccnstruction Practices (30105)
E p<oyee Cencerns: ine folle>:ing tnroe specific and unrelated concerns were eveluated in revisien 3 of this element report, dated Feervary 7, 4957: ,
"Impreper ounting of limit 5,< itches on 2 FCV-30-15."
r
- 1. u.AS-56-007. :
- 2. RCM-85-001:
Faited check valve on B-CST allowed water on top of bladcer. Bladder could get into ERCW suction."
- 3. 1-56-233-SCN: " An anonymous individual mailed in a potential safety nazard , associated with the condensate demineralizer waste evaporator (CDVE) on elevation 706 of the Auxiliary Building at Sequoyah Nuclear :
Plant (SCN). The original stainless steel piping for pumping "Bottoms" from the CCWE was removed and replaced b.v a temporary rubber hose. Extensive modifications are being performed over the hose.
- Welding hot chips have been cbserved falling on the ruocer hose. Damage to or rupture of the hose wovid result in possible personnel exposure of a Sign a-ount." ,
These three concerns ae specific to SCN. Concerns PAS-86-002 i a c R:v-55-::: -e e deter-ice :) T '.' A te be c:te9tially nuclear t j 5 & f e *. ., r e l &
a 4
0911220303 G811Q4 PUR ADOCN 0500u327 PDC p
. i II. Sue arv of Issues !
- 1. MAS-86-002: The issue defined by TVA is that a mounting problem with 20hE limit switches (ZS) on t'utterfly valves with circular ;
novecent of the actuator was identified for six Systerr 30 (contain- '
, ment ourc0 valves. This condition had been identified by the SON '
electrical maintenance sect. ion as a result of a one-time fielt' '
inspection under SMI-0-0-1 to verify the installation of qualified j switches in accordance with 10 CFR 50.49 requirements, i i
- 2. RCM-85-001: The issue defined by TVA is that five styrofoam float !
(che:k.) valves at the top of the B-CST failed to properly seal due '
to shrinkage of the styrofoar discs. Additionally, TVA evaluated >
the possibility of the CST bla._er being drawn into the AFV suction j line, potentially clogging the line downstream of the ERCW suction .
! and ci.using loss of auxiliary feedwater.
l l
- 3. I-$6-253-50N: The concern is whether personnel could be exposed to j
a raciological ha:ard due t'o rupture or damage to the rubber hese ,
used to transfer bottoms, offgrade distillate, and distillate from i j
the CDWE to tre Floor Drain Collector Tank (FDCT). TVA focused their i
evaluation on the transfer of highly radioactive bottoms rather than f the slightly radioactive offgrade distillate. Due to the impossibil-
) ity of cerrari g the tire when work that could potentially damage the l hose was occurring and COWE bottoms were being transferred tnrough i the hcse, T"A took the approach of showing that administrative
- centeel of the cottoms trant,fer operation would prevent personnel
l' frc accessing aress through which the hose runs during transfer l Operations, there0y rreventing excessive personnel exposure. i J
) III. Eva hat
} 1. MAS-36-002: TVA's investigation consisted of reviewing documenta- f i tion between the Maintenance and Modifications Departments that !
- aedressed the ZS mounting problem. The six system 30 valves alleged l l to have 25 mi slignment problems severe enough to warrant correction 3
were discoversd during a one-time field inspection to verify that '
{ 25 installation conformed to 10 CFR 50.49 requirements. The modifi- :
1 cation department's investigation of the six system 30 ZSs alleged by '
the Electrical Maintenance section to be counted incorrectly resulted +
j in a cetermination that only one of tNse 255 (2-Z5-30-15) wa s !
i mounted incorrectly. This situation vas corrected by work request i
- E-110369 on 4/11/96. Maintenance concurred with modification's l assess ent of the problem and the corrective action taken. An 7
' tervie. .a tn tne ele:trical Maintenance section supervisor deter- !
mined that concurrence was based on the fact that the post-modifica- !
tion testing of the otner five system valves was satisfactory in l c
spite of tre slight misalignment of the switch actuation lever arm i
! with tre circular strike plate. Additionally, the section supervisor !
} stated t*at r syste- 30 valve cositien indication failures base j
- _ ,: :a u -4 sa ng et ec w :. er 1 e :ss. at :.;-
i
- t*P. t*e .* ting prCDle with 2-25*30-15 wa s !
- W tt . c ' t *- P c:Prectiet Of similar 25 counts required. TkA, (
I
- eref et. c0Pel6ced t*at PO further Corrective action is recuired.
1
- 2. RCv-55-001: An interview with a ecdification engineer at SCN revealed that the check valve problem was fixed by replacing the styrefcar discs with nonshrinkable plastic discs under ECN L6515.
Tne work was completed on 3/27/E6 under work plan 11844 Ne further preolems with the check valves have occurred since the modification was cerclete . TVA concluded that no further corrective action is required.
Rega ding the issue of the bladder being drawn into the AFV suction line, this concern was validated. TVA modified the inlet grating to the AFW su: tion line to prevent the bladder from being drawn into the line ccanstreat. of the ERCW suction. The work was completed on 3/27/86 under w0rk plan 11844 TVA confirmed that no tanks other tnan the A anc B C5is were effected by this concern.
- 3. I-Sf-233-SON: TVA cerformed e ployee interviews and reviewed SQN c;e-atir; instrv:tieni. radiological instructions, and HP survey re:cres to as:ertain whether controls were sufficient to prevent personnel f ro- being in the pecximity of the hose during better.s transfer operatiens. TVA aise confirmed that the offgrade distillate was ret $1;n'y racica:tive and, therefore, controls to limit access to areas th cu;n which the hese runs are not required aad are not im;tsed curing of fgrace distillate transfer to the FDCT. TVA's revie- 24 501-77.153 and ROI-13 confireed that these procedures recuire W? notification by operators prior to the commen:ement of bott: .s trarsfer ::eratiers so that HP can icek and monitor areas th*cugh wnich the hose *uns. These procedures further require that tnc hote be flushed ard surveyed for hot spots oy 'AP prior to lif ting the a: cess restrictions urder RCI-13. TVA verified proper imple?en-tatten of these controls by citing a particular example in which they were ade:uately ef fected (11/29/86 bottems transfer). TVA, there-fere, con:1uded that these controls are sufficient to prevent person-nel a::ess (aad the resultant potential exposure) or work in areas wnere the hose runs during b0ttems transfer, and these controls have been preper y irpler.ented for past be* toms transfer o p e ra t', o n s .
Although the ele ent report states that no corrective action is re;uired, TVA has issue: an EON to replace tre rubber hose with pe manent piping.
IV. Coa: 1us4e s The N;; ,taff celieses tnat the TVA investigation of the three e picyee con: erns accresse: cy this ele ent report is aceovate, and their resolution of tne cen: erns in revision 3 of the eierent report is a; epta:le fe* resta*t.