ML20005B610: Difference between revisions
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| number = ML20005B610 | | number = ML20005B610 | ||
| issue date = 07/02/1981 | | issue date = 07/02/1981 | ||
| title = Responds to NRC | | title = Responds to NRC Re Safety Concerns Associated W/Pipe Breaks in BWR Scram Sys.Consequences of NUREG-0785 Scenario Are Not Applicable.Containment Temp Sensors Are Located in Area of SDV Piping Headers | ||
| author name = Davidson D | | author name = Davidson D | ||
| author affiliation = CLEVELAND ELECTRIC ILLUMINATING CO. | | author affiliation = CLEVELAND ELECTRIC ILLUMINATING CO. | ||
| Line 12: | Line 12: | ||
| case reference number = RTR-NUREG-0785, RTR-NUREG-785 | | case reference number = RTR-NUREG-0785, RTR-NUREG-785 | ||
| document report number = NUDOCS 8107080436 | | document report number = NUDOCS 8107080436 | ||
| title reference date = 05-05-1981 | |||
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC | | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC | ||
| page count = 1 | | page count = 1 | ||
| Line 17: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:- | ||
T H E C L E V E L A N D E L E C T r l C ; L L U M I N AT I N G C O M P A N '.' | |||
'O r 5000 e CLEVEL AND oHlo 44101 e TELEPHONE ut6) 622-9800 e ILLUMIN ATING BLDG e 55 PUBLIC SoU AM Semng The Best Location in the Nation DJwyn R. Davidson i PRESIDENT LO M | |||
ATEM ENGINEERING AND CONSTRUCTICN 4 | |||
July 2, 1981 se-Mr. Robert L. Tedesco, Assistant Director i | |||
JUL 0 7 L9siw iB Division of Licensing | |||
* 7 v.s. Mxuas % D U. S. Nuclear Regulatory Commission | |||
" "808 Washington, D. C. 20555 | |||
's y k | |||
~ | |||
Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Scram Discharge Volume Pipe Freak | Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Scram Discharge Volume Pipe Freak | ||
==Dear Mr. Tedesco:== | ==Dear Mr. Tedesco:== | ||
In response to your {{letter dated|date=May 5, 1981|text=letter dated May 5,1981}}, on the subject of " Safety Concerns Associated with Pipe Breaks in the BWR Scram System," we reference the General Electric Report IEDO-24342 which was transmitted with GE's letter MFN-091-81 from Glenn G. Sherwood to Darrell Eisenhut dated April 30, 1981. This report provides the results of the GE generic evaluation of BWR scram discharge piping i | |||
In response to your letter dated May 5,1981, on the subject of " Safety Concerns Associated with Pipe Breaks in the BWR Scram System," we reference the General Electric Report IEDO-24342 which was transmitted with GE's letter MFN-091-81 from Glenn G. Sherwood to Darrell Eisenhut dated April 30, 1981. This report provides the results of the GE generic evaluation of BWR scram discharge piping | breaks as required by Items 1, 2, and 3 of your letter. Our review of the report l | ||
confirms the applicability to the Ferry Plant with the following additional in-formation, i | |||
Since Ferry utilizes a Mark III containment design arrangement, the consequences of the scenario postulated in NUnEG-0785 are not applicable. | |||
This is because the scram discharge volume (SDV) is inside the primary containment while the core cooling and heat removal pumps are all outside containment in the auxiliary build-ing. Any water discharged from an SDV pipe break will return directly to the suppression pool and the postulated common mode failure due to equipment flooding is not present. | |||
Thus, tnere is no threat to the long term cooling capability provided by the Ttergency Core Cooling Systems. | |||
Also, containment temperature sensors are located in the vicinity of the SDV piping headers. These safety grade instruments would provide indication of a pipe rupture in such areas. | Also, containment temperature sensors are located in the vicinity of the SDV piping headers. These safety grade instruments would provide indication of a pipe rupture in such areas. | ||
We believe that the information in NEDO-24342 also addresses much of 120-day plant-specific response requirements; however, we will be submitting a Ferry plant spe-cific response by September 16, 1981. | We believe that the information in NEDO-24342 also addresses much of 120-day plant-specific response requirements; however, we will be submitting a Ferry plant spe-cific response by September 16, 1981. | ||
If you have further questions, please let us know. | If you have further questions, please let us know. | ||
Very truly yours, I B107080436 810702 | Very truly yours, I B107080436 810702 | ||
^ | |||
):PDR ADOCK 05000440 (A | |||
PDR Dalwyn d. Davidson, Vice President System Engineering and Construction | |||
#pk DRD:dlp cc: | |||
G. Charnoff, J. Haghes, Resident Inspector hi P | |||
_ _ _ _ _ _ _ _ _}} | _ _ _ _ _ _ _ _ _}} | ||
Latest revision as of 10:07, 23 December 2024
| ML20005B610 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 07/02/1981 |
| From: | Davidson D CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | Tedesco R Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0785, RTR-NUREG-785 NUDOCS 8107080436 | |
| Download: ML20005B610 (1) | |
Text
-
T H E C L E V E L A N D E L E C T r l C ; L L U M I N AT I N G C O M P A N '.'
'O r 5000 e CLEVEL AND oHlo 44101 e TELEPHONE ut6) 622-9800 e ILLUMIN ATING BLDG e 55 PUBLIC SoU AM Semng The Best Location in the Nation DJwyn R. Davidson i PRESIDENT LO M
ATEM ENGINEERING AND CONSTRUCTICN 4
July 2, 1981 se-Mr. Robert L. Tedesco, Assistant Director i
JUL 0 7 L9siw iB Division of Licensing
- 7 v.s. Mxuas % D U. S. Nuclear Regulatory Commission
" "808 Washington, D. C. 20555
's y k
~
Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Scram Discharge Volume Pipe Freak
Dear Mr. Tedesco:
In response to your letter dated May 5,1981, on the subject of " Safety Concerns Associated with Pipe Breaks in the BWR Scram System," we reference the General Electric Report IEDO-24342 which was transmitted with GE's letter MFN-091-81 from Glenn G. Sherwood to Darrell Eisenhut dated April 30, 1981. This report provides the results of the GE generic evaluation of BWR scram discharge piping i
breaks as required by Items 1, 2, and 3 of your letter. Our review of the report l
confirms the applicability to the Ferry Plant with the following additional in-formation, i
Since Ferry utilizes a Mark III containment design arrangement, the consequences of the scenario postulated in NUnEG-0785 are not applicable.
This is because the scram discharge volume (SDV) is inside the primary containment while the core cooling and heat removal pumps are all outside containment in the auxiliary build-ing. Any water discharged from an SDV pipe break will return directly to the suppression pool and the postulated common mode failure due to equipment flooding is not present.
Thus, tnere is no threat to the long term cooling capability provided by the Ttergency Core Cooling Systems.
Also, containment temperature sensors are located in the vicinity of the SDV piping headers. These safety grade instruments would provide indication of a pipe rupture in such areas.
We believe that the information in NEDO-24342 also addresses much of 120-day plant-specific response requirements; however, we will be submitting a Ferry plant spe-cific response by September 16, 1981.
If you have further questions, please let us know.
Very truly yours, I B107080436 810702
^
):PDR ADOCK 05000440 (A
PDR Dalwyn d. Davidson, Vice President System Engineering and Construction
- pk DRD:dlp cc:
G. Charnoff, J. Haghes, Resident Inspector hi P
_ _ _ _ _ _ _ _ _