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MONTHYEARIR 05000312/19820161982-05-0505 May 1982
IE Insp Rept 50-312/82-16 on 820401-0502.No Noncompliance Noted.Major Areas Inspected:Operational Safety verification,long-term Shutdown Activities,Maint & Surveillance Observations & Followup on Regional Requests
Project stage: Request
ML20052H4161982-05-10010 May 1982
Summary of 820423 Meeting W/Utils in Bethesda,Md Re Auxiliary Feedwater Header Damage in Certain B&W Plants. Agenda Encl
Project stage: Meeting
ML20054G5841982-05-20020 May 1982
Submits Addl Info Re Auxiliary Feedwater Header Mod,Per NRC Request.Existing Headers Have Become Distorted Since Original Fabrication.Headers Will Be Replaced & Stabilized to Prevent Further Unacceptable Damage to Steam Generators
Project stage: Other
ML20053A4681982-05-20020 May 1982
Forwards 820429 & 0505 Ltrs Re RO 82-09 on Repairs to HPI Nozzles, & RO 82-10 Re Deformations in Auxiliary Feedwater Header Ring & Proposed TMI Requirements.Encl Consists of Info Sent to NRC After Util 820421 Rept to Aslab.W/O Ltrs
Project stage: Other
ML20054G9991982-05-20020 May 1982
Submits Details Re Mod of once-through Steam Generator Auxiliary Feedwater Header,Per NRC Request at 820518 Meeting.Sketches Encl
Project stage: Meeting
ML20053E4371982-05-21021 May 1982
Submits Agreements Reached During 820518 Discussions Re Anticipated Mods to Steam Generator Auxiliary Feedwater Distribution Headers.Written Work Scope for Attaching Nozzle Flange Prior to Work on Steam Generator Expected
Project stage: Other
ML20054J0091982-06-0909 June 1982
Responds to 820608 Telecopy Re Preliminary Description of Stabilization of Steam Generator Internal Auxiliary Feedwater Headers.Util Can Proceed W/Internal Header Stabilization as Described Based on Review & 820609 Telcons
Project stage: Other
ML16299A3811982-06-15015 June 1982
Notification of 820624 Meeting W/Util & B&W Owners Task Task Group in Bethesda,Md to Discuss Generic Repairs & Design Mods Re Damaged Auxiliary Feedwater Header Inside Steam Generators
Project stage: Meeting
ML20054J4821982-06-23023 June 1982
Requests Addl Info Re Auxiliary Feedwater Header Repair, Reported in LER 82-10.Response Should Be Provided 10 Days Prior to Scheduled Restart
Project stage: Other
05000368/LER-1982-020-03, /03L-0:on 820529,during Power Escalation,Battery Bank 2D01 Voltage Dropped to 121-volts Dc.Caused by Primary Voltage Supply to Inverters 2Y-11,2Y-13 & 2Y-25 Switching to Battery Bank 2D011982-06-25025 June 1982
/03L-0:on 820529,during Power Escalation,Battery Bank 2D01 Voltage Dropped to 121-volts Dc.Caused by Primary Voltage Supply to Inverters 2Y-11,2Y-13 & 2Y-25 Switching to Battery Bank 2D01
Project stage: Other
ML20062D6171982-07-0101 July 1982
Evaluation,Repair & Replacement of Damaged Internal Auxiliary Feedwater Header at Davis Besse 1,Oconee 3 & Rancho Seco
Project stage: Other
ML20062D5971982-08-0303 August 1982
Forwards BAW-1732, Evaluation,Repair & Replacement of Damaged Internal Auxiliary Feedwater Header at Davis Besse 1,Oconee 3 & Rancho Seco, Per 820624 Meeting W/Nrc in Bethesda,Md & NRC 820623 Request.Response Summary Submitted
Project stage: Meeting
ML20027B5391982-09-13013 September 1982
Forwards Requested Info Re Auxiliary Feedwater Stabilized Internal Header.Includes B&W Info Re Commitment to Prepare Design Rept for Modified Steam Generator & Auxiliary Feedwater Piping Sys
Project stage: Other
05000298/LER-1983-011-01, /01T-0:on 830710,welds CSA-BJ-5 & 6 Found Leaking During Grinding of Weld Crowns.Caused by Intergranular Stress Corrosion Cracking.Welds to Be Repaired by Weld Overlay Methods.Piping Will Be Replaced1983-07-20020 July 1983
/01T-0:on 830710,welds CSA-BJ-5 & 6 Found Leaking During Grinding of Weld Crowns.Caused by Intergranular Stress Corrosion Cracking.Welds to Be Repaired by Weld Overlay Methods.Piping Will Be Replaced
Project stage: Other
ML20024D9811983-07-28028 July 1983
Advises That Responsibility for Evaluating Proposed Actions Re IE Bulletin 83-02 Concerning Recirculation Sys Pipe Cracks Transferred to Div of Licensing
Project stage: Other
A830019, Forwards Info Re Intergranular Stress Corrosion Cracking Observed in Core Spray & Reactor Water Cleanup Sys,Per 830822 Request.Weld Overlay Repairs Meet Safety Margins of App X to Section IX of ASME Code1983-08-23023 August 1983
Forwards Info Re Intergranular Stress Corrosion Cracking Observed in Core Spray & Reactor Water Cleanup Sys,Per 830822 Request.Weld Overlay Repairs Meet Safety Margins of App X to Section IX of ASME Code
Project stage: Other
ML20080D8231983-08-25025 August 1983
Revised Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements of Coolant Leakage During Cycle 9 Operation
Project stage: Other
ML20080D8071983-08-25025 August 1983
Forwards Revised Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements of Coolant Leakage, During Cycle 9 Operation,Per 830824 Request
Project stage: Other
1982-06-09
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Text
,n, (JSMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street, Box 15830, Sacramento, Califomia 95813; (916) 452-3211 September 13, 1982 i
DIRECTOR OF NUCLEAR REACTOR REGULATION ATTN: J F STOLZ, CHIEF OPERATING REACTORS, BRANCH 4 V S NUCLEAR REGULATORY COMMISSION WASHINGTON DC 20555 DOCKET N0. 50-312 RANCHO SEC0 NUCLEAR GENERATING STATION UNIT N0 1 RESPONSES TO NRC QUESTIONS ON AFW HEADER In response to your request for additional information regarding the stabilized internal header, as well as your request for a commitment to prepare a Design Report for the modified steam generator and auxiliary feedwater piping systems, the attached information, supplied by Babcock and Wilcox, is provided.
!, [ 2/ tin,h ohn Mattimoe Assistant General Manager and Chief Engineer 00/
Attachments J
l 820 9 210 2.2 7 p AN ELECTRIC SYSTEM SERVING MORE THAN 600.000 IN THE If E A R I 0F CALIFORNIA 1
RESPONSES TO NRC QUESTIONS ON AFW HEADER Question 1.
Provide a summary of the analyses performed to assure that A.
the structural integrity of the stabilized internal headers will be maintained for the remaining life of the plant.
Include a description of all forcing functions associated with ASME levels A, B, C, and D n' odes. A brief description of the analyses performed and a summary of the results of the analyses.
Response
Summary of Analysis of Stabilized Header The stabilization analysis is included in B&W calculation 32-1134668-00.
(BAW 1732, Section 8.0, Reference 7)
The following loading conditions were considered:
Normal and Upset Conditions (Now called Service Levels A and B)
Dead Weight, Flow Induced Vibration, Operating Basis Earthquake, and Thermal Transients were considered.
This includes a fatigue analysis to demonstrate structural integrity for the plant life.
- Emergency Condition (Now called Service Level C)
Dead Weight, Flow Induced Vibration, Safe Shutdown Earthquake, and Thermal Transients were considered.
- Faulted Condition (Now called Service Level D)
Two load combinations were considered:
(1) Dead Weight, LOCA, and Safe Shutdown Earthquake; (2) Dead Weight, Main Steam Line Break, and Safe Shutdown Earthquake.
The box header corner welds have recently been analyzed for these conditions and have been shown adequate. This analy-sis will be incorporated in 32-1134668-00.
Complete corner weld integrity was assumed.
Question 1.
Since the inlet opening to the internal headers will not be B.
closed, provide assurance that steam pockets cannot still be trapped in the header and cause additional damage in the event of their collapse.
Response
Although the 6" inlet hole and the sixty (60) 11" holes remain in the internal header, a steam condensation problem is not anticipated because of the absence in the header of water below saturation temperature. Auxiliary Feedwater
Responses to NRC Questions on AFW Header Question 1.B.
Response
(Continued) will now be injected into the tube bundle below the bottom of the header. This will prevent any cold water from.
entering the internal header and thus prevent steam conden-sation pressure fluctuations.
Question 2.
Provide a commitment to prepare the ASME Section III required Design Reports for the modified steam generators and auxiliary feedwater piping systems.
Response
The Stress Report issued when the steam generators were fab-ricated is what is now called the Design Report. The Field Change Authorization (FCA) revising this report to incorporate the changes to the header is being prepared for each licensee by Babcock & Wilcox.
.