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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20210L4361999-08-0202 August 1999
Cycle 9 12-Month SG Insp Rept
ML20210L4451999-07-31031 July 1999
Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept
ML20211F9031999-06-30030 June 1999
Cycle 9 Refueling Outage
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML20205B6631999-02-28028 February 1999
Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys
ML20198S7301998-12-31031 December 1998
Cycle 10 Voltage-Based Repair Criteria 90-Day Rept
ML20199J2571998-01-31031 January 1998
Cycle 9 Voltage-Based Repair Criteria 90-Day Rept
ML20199J2441998-01-29029 January 1998
Snp Unit 2 Cycle Refueling Outage Oct 1997
L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997
SG Secondary Side Loose Object Safety Evaluation
ML20203B9591997-09-18018 September 1997
Pressure Locking Summary & Evaluations Using Commonwealth Edison Methodology for Sqn
ML20210J1761997-07-31031 July 1997
Unit 1,Cycle 9 Alternate Plugging Criteria 90 Day Rept
ML20138D1991997-04-0404 April 1997
Special Project97-928S, Sequoyah Nuclear Plant Assessments
ML20138C5371997-03-24024 March 1997
Rev 0 to Pressurizer Level Event
ML20217G2401997-03-0303 March 1997
Non-proprietary Rev 0 to SE of Reduced Thermal Design Flow
ML20117J3611996-08-0101 August 1996
SE of Safety Valve Setpoint Tolerance Relaxation
ML20117K9461996-03-0505 March 1996
Reliability Study
ML20117K9511996-02-29029 February 1996
Reliability Common Cause Assessment, for Feb 1996
ML20095J1891995-10-0505 October 1995
Design & Analysis of Weld Overlay Repair for Sequoyah Unit 1 CRDM Lower Canopy Seal Welds
ML20081D3831995-03-12012 March 1995
Simulator Four Yr Test Rept for 950312
ML20083N9521994-11-16016 November 1994
10CFR50.59 Rept to Nrc
ML20024H8491993-07-19019 July 1993
Evaluation of Ultrasonic Test Results from 1993 ISI on Underclad Flaw Indications in Sequoyah,Unit 1 Rv Nozzles.
ML20118D1941992-09-21021 September 1992
Technical Rept on Hydrogen Control Measures & Effects of Hydrogen Burns on Safety Equipment
ML20114A6641992-08-15015 August 1992
920619 Self-Assessment. Several Hardware & Software Enhancements to Emergency Response Ctrs Completed During Reporting Period
ML20141M1341992-03-27027 March 1992
Spent Fuel Pool Mod for Increased Storage Capacity
ML20029C2011991-03-12012 March 1991
Initial Simulator Certification.
ML20028H8591990-09-0707 September 1990
Nuclear Quality Audit & Evaluation Review Rept, Sequoyah Nuclear Plant Look Back Review of Cable Issues.
ML20136J0431990-06-30030 June 1990
Criticality Analysis of Sequoyah Units 1 & 2 Fresh Fuel Racks
ML20043B6061990-05-11011 May 1990
Diesel Generator Voltage Response Improvement Rept.
ML20006E5771990-02-0505 February 1990
Rev 1 to Sequoyah Units 1 & 2 Spent Fuel Storage Rack Criticality Analysis.
ML20246D5351989-02-28028 February 1989
Steam Generator Tubing Insp Results
ML20247H1301988-11-30030 November 1988
Rev 0 to Structural Analysis & Evaluation of Sequoyah Reactor Coolant Pump Support Columns
ML20236D1951988-11-18018 November 1988
HVAC Damping Values
ML20134H6801988-09-0202 September 1988
Technical Evaluation of Procurement of Matls & Svcs
ML20245B4181988-08-17017 August 1988
Investigation Rept,Design & Operation of Sampling Sys for Analysis of High Purity Water
ML20151Q2691988-08-0101 August 1988
Final Rept on IE Bulletin 79-14 for Tva,Sequoyah Nuclear Plant Unit 1 & Common Piping
ML20155J5721988-07-31031 July 1988
Assessment of Structural Adequacy of Concrete Foundation Cells for Emergency Raw Cooling Water Pumping Station & Access Roadway
ML20207F6231988-07-0505 July 1988
Evaluation of Effects of Postulated Pipe Failures Outside of Containment for Sequayah Nuclear Plant,Units 1 & 2
ML20207B6301988-06-27027 June 1988
Engineering Assurance Oversight Review Rept,Sequoyah Nuclear Plant - Unit 1,Design Baseline & Verification Program
ML20147G9961988-03-31031 March 1988
Review of Operational Readiness Corrective Actions. Related Documentation Encl
ML20147H6331988-02-29029 February 1988
Plant,Diesel Generator Evaluation Rept
ML20147G7861988-02-25025 February 1988
Task Rept on Development of Seismic Acceleration Response Spectra for Diesel Generator Bldg of Sequoyah Nuclear Plant, Part 1:Design Basis SSE Input
ML20147G8041988-02-25025 February 1988
Task Rept on Development of Seismic Acceleration Response Spectra for Diesel Generator Bldg of Sequoyah Nuclear Plant, Part 2:Site-Specific OBE & SSE Inputs
ML20234F2111988-01-0505 January 1988
Rept of Sequoyah Readiness Review
ML20147F0581987-12-0202 December 1987
Non-linear Time History Seismic Response Analyses for ERCW Cell, Task Rept
ML20236B3481987-10-15015 October 1987
Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 207.4(B), Deviation Documentation:Caq Documentation
ML20236B3511987-10-14014 October 1987
Rev 0 to TVA Employee Concerns Special Program Sequoyah Element Rept 232.8(B), Piping & Valve Design:Criteria for Min Pipe Wall Thickness
ML20236B3541987-10-14014 October 1987
Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 235.2(B), Electrical Safety:Exposed 480 Volt Bus at Panel Top
ML20236B3441987-10-14014 October 1987
Rev 0 to TVA Employee Concerns Special Program Sequoyah Element Rept 204.9(B), Use of Reverse Prints
ML20236B3581987-10-14014 October 1987
Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 241.4(B), Cable Termination & Splices:Amphenol Connector
ML20236Q2011987-10-0101 October 1987
Temp Measurement Rept for Long-Term Current Test on Littlefuse,Flas-5,5 Amp Fuses
1999-08-02
[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
-_ ,
- TVA EMPIhYEE CONCERNS REPORT NUMBER: 33
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SPECIAL PROGRAM REPORT TYPE: Sequoyah Nuclear Plant Element REVISION NUMBER:- 2 TITLE: Operability of Containment Spray Pump REASON FOR REVISION: To incorporate TAS and SRP comments.
SWEC
SUMMARY
STATEMENT: The item in this report was identified by the Nuclear Regulatory Commission (NRC) and was included in the Stone & Webster Engineering Corporation (SWEC) systematic analysis. The' item evaluated within this report was verified to be adequately addressed. SWEC Concern A02850620007-001 will be ready for NRC closure following completion of corrective actions.
PREPARATION PREPARED BY:
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- SRP Secretary's signature denotes SRP concurrences are in files.
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Title:
Operability of Containment Spray Pump SWEC Concerns: A02850620007-001 Source Document: NRC Inspection Report 50-327, 328/85-18 Report Number: SWEC-SQN-33 l
Evaluator: N[ Net Jd /J- -1 f(-
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Re: lowed by: N WD'b.Y /k 36!$b J. J. : nightly Date l-Approved by: dA /4/Jo/#,
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SWEC-SQN-33 l NRC Report 50-327/85-18-01 I. INTRODUCTION During an inspection on May 27-31, 1985 (Reference 1) the Nuclear j Regulatory Commission (NRC) inspector identified the containment spray pump 1A low flowrate as unresolved issue 50-327/85-18-01. This !
unresolved issue was included in the Stone & Webster Engineering Corporation (SWEC) systematic analysis as follows: <
l A02850620007-001 operability of containment spray pump 1-A (Unit 1).
Information on the background, the corrective actions taken, the i verification methodology, the verification analysis, the completion status, and any pertinent references for the area of concern is included in this report.
II. VERIFICATION OF SWEC ISSUE A. BACKGROUND The NRC Inspection Report (Reference 1) described the background as follows:
During his audit of data documented for Containment Spray Pump 1A (Unit 1), the inspector observed that the pump flowrate during the. initial tests was > 5500 gpm but dropped to 3500-4000 gpm in April 1981 and thereafter. The test data for the differential pressure ( AP) of this pump remained 132 to 145 psi during the operational life of the pump, thereby indicating l that the pump had remained operable. The licensee was not able l to explain the drop in flowrate or why the flowrate was allowed to remain below the rated 4700 gpm that is designated on the drawing for this system.
The 1974 edition Summer 1975 addenda, of the ASME Boiler and Pressure Vessel Code (paragraph IWP-3110) s_tates that "in a fixed resistance system, it is required to measure AP or Q (flowrate), not both." All later editions of the Code require I that both AP and Q be measured. The NRC staff endorses the I positions of the later Codes. Inasmuch as the licensee j documented both AP and Q, it is necessary to establish the l reason for the change in Q only and whether or not the pump has l been in a degraded condition since April 1981. The inspector l designated this matter as Unresolved Issue 50-327/85-18-01, l Operability of Containment Spray Pump 1A. TVA committed to l
expedite review and resolution of this issue.
1
! Page 1 of 3
r .
. '- 7 B. CORRECTION-ACTION TAKEN The SQN mechanical test engineer stated to ECTG that an investigation 1 was performed concerning the flowrate for containment spray pump 1A l (unit 1). This investigation identified a damaged flow element I (1-FE-72-34). ECN Number.L6674 (reference 2) was approved l June 2, 1986'for replacement of this flow element, which was ordered l under requisition number 453114. !
lR1 The mechanical test engineering supervisor stated to ECTG that the 1 test data for the differential pressure (AP) of-this pump remained l 132 to 145 pounds por square inch differential (PSID).during the I i
operational life of the pump, thereby indicating the pump has not I been in a degraded condition. It had been SQN's view that-the l adequate AP was sufficient to satisfy ASME code requirements. .
I For this reason, SQN did.not act promptly to correct the deficient
~
l flowrate indication. I SQN's commitment to measure pump flowrate is now identified as a 1 i- punch list item (i.e. change in process) in surveillance instruction- lR2 (SI) - 37, " Containment Spray Pump Test," Revision 27. l C. VERIFICATION METHODOLOGY The SWEC concern identified for ECTG verification was stated as follows:
RIMS Number Issue RIMS Item A02850620007-001 Flowrate for 'Contain- RIMS-001 i
ment Spray Pump 1A Unit 1 l
dropped below the required 4700 GPM without a reason established as required by the Code.
ECTG reviewed the Sequoyah Compliance Licensing files for internal and external correspondence related to this issue and the NRC status and tracking system for the issue. This review of the pertinent documentation, in addition to discussion with the SQN Mechanical-Test Engineer, formed the basis for this verification activity.
D. VERIFICATION ANALYSIS ECTG verified that the SQN corrective actions for this concern have j
been initiated. It is expected that installation of the replacement
- flow element will restore the flow indication of Containment Spray Pump 1A. ' Incorporation of the flowrate measurement requirement into lR2 the surveillance instruction SI-37 is pending. I i
Page 2 of 3
-__. ._ _ . _ . _ - _ _ _ _ _ . . . . . . . _ _ _ _ . ~ _ _
= V 1
..s. _
E. COMPLETION STATUS The SWEC issue is being adequately addressed by TVA and SQN. Upon implementation of the corrective actions in this area documented by ECN L6674 (Reference 2) and incorporation of the flowrate requirement lR2 into the surveillance instruction SI-37, the SWEC issue will be l complete and ready for NRC closure. -Until that time, this issue remains open.
III. REFERENCES
- 1. NRC Inspection Report Nos. 50-327/85-18 and 50-328/85-18, dated June 19, 1985, D. M. Verre111 to H. G. Parris
- 2. Engineering Change Notice (ECN) L6674, dated June 2, 1986 (RIMS 825 860603 517)
N
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l Page 3 of 3
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