ML18044A855
| ML18044A855 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 05/09/1980 |
| From: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| IEB-79-17, NUDOCS 8005130457 | |
| Download: ML18044A855 (4) | |
Text
.e consumers Power company 8 005130"157 General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
- Area Code 517 788-0550 May 9, 1980 Mr James G Keppler Off ice of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - RESPONSE TO IE BULLETIN 79-17, PIPE CRACKS IN STAGNANT BORATED WATER SYSTEMS AT PWR PLANTS Consumers Power Company was requested to provide information as outlined in IE Bulletin 79-17, pipe cracks in stagnant borated water systems at PWR plants.
The requested information was submitted to the staff by letters dated August 25, 1979 and February 1, 1980.
This letter constitutes the final report for the subject bulletin as it applies to the Palisades Plant.
During the 1979/1980 Palisades refueling outage, ultrasonic examinations and hydro/leak tests were conducted on stainless steel piping lines which have been postulated to contain stagnant borated oxygenated water.
The examinations and tests were performed partially in response to the normal Inservice Inspection Program at the Palisades Nuclear Plant and partially in response to IE Bulletin 79-17.
This report documents the results of the examinations and testing of the piping runs identified as stagnant.
Forty-five (45) stainless steel welds (Attachments 1 and 2) were ultrasonically examined in accordance with the 1974 Edition of Section XI, ASME Code, with Addenda through Summer 1975.
Additionally, all technical requirements from Appendix III of the Winter 1975 Edition of that Code were also met.
The results of the ultrasonic testing demonstrated that no defects or cracks were found.
The welds selected for examination canvassed all areas identified as stagnant and pipe diameters/wall thickness in accordance with IE Bulletin 79-17.
Aool
.s 1/1
-I
The data from the ultrasonic examinations and hydro/leak tests, including all personnel and equipment certifications, material certifications, testing procedures, etc, will be included in the Inservice*Inspection Final Report.
David P Hoffman (Signed)
David P Hoffman Nuclear Licensing Administrator CC Director, Office of Nuclear. Reactor Regulation Director, Office of Inspection and Enforcement NRC Re.sident Inspector-Palisades Attachment 2 Pages 2
ATTACHMENT 1 Compilation of stainless steel welds examined/tested during the 1979/1980 Palisades outage which have been postulated to contain stagnant borated oxygenated water.
Containment Spray ESS-10-CSS-SLB-201 ESS-8-CSS-SLB-212 ESS-8-CSS-SLB-219 High-Pressure Safety Injection ESS-6-SIS-lHP-201*
ESS-6-SIS-lHP-203*
ESS-.6,-SIS-2HP-209 ESS-6-SIS-3HP-206 ESS-4-SIS-HPB-204 ESS-4-SIS-HPB-210 ESS-3-SIS-HPA-235 ESS-3-SIS-HPB-230 ESS-3-SIS-HPC-214 ESS-3-SIS-HPC-216 ESS-3-SIS-3HP-201 Low-Pressure Safety Injection/
Shutdown Cooling ESS-10-SIS-LPB-220*
ESS-12-SIS-lLP-210*
ESS-12-SIS-lLP-221*
ESS-12-SIS-lLP-225*
ESS-12-SIS-lLP-229*
ESS-10-SDC-XIA-201*
ESS-10-SDC-XOA-208*
ESS-10-SDC-XOB-205*
ESS-10-SDC-XC0-205*
Chemical Volume and Control CVC-4-BAI-1P4-205 CVC-4-BAI-1P4-206 CVC-4-BAI-1P6-201 CVC-4-BAI-1P7-201 CVC-4-BAP-SBL-201 CVC-4-BAP-SLB-201 CVC-3-BAI-1P2-203 CVC-3-BAI-1P7-232 CVC-3-BAI-1P8-205
(
Radwaste RWS-6-CWR-SL4-202 RWS-4-CWT~lPl-203 Spent Fuel Pool SFP-14-FPF-RLl-303 SFP-8-CPL-DLl-301 SFP-8-CPL-DLl-320 SFP-8-CPL-DLl-321 SFP-8-FPF-RLl-304 SFP-6-SRT-SLl-222 SFP-6-SRT-SLl-224 SFP-6-SRT-SLl-225 SFP-6-SRT-RLl-225 SFP-3-FPP-FPB-301 SFP-3~FPP-FPB-303
~b"'Hydro/Leak Tests Containment Spray (Hydro)
HPSI (Hydro)
LPSI (Hydro)
SI Bottle Discharge (Hydro)
Spent Fuel Pool (Hydro)
Boric Acid (Hydro)
Radwaste (Inservice Test)
- Examined per normal Section XI requirements.
~"~"'Hydro/leak tets are currently being conducted and will be completed prior to plant start-up.
ATTACHMENT 2 Verification of Compliance - IE Bulletin 79-17 System Containment Spray High-Pressure Safety Injection Low-Pressure Safety Injection/
Shutdown Cooling Spent Fuel Pool Cooling Boric Acid Radwaste No Required To Be Examined 3
9 8
7 2
Number Examined 3
11 9
11 9
2