ML20079L466: Difference between revisions
StriderTol (talk | contribs) (StriderTol Bot insert) |
StriderTol (talk | contribs) (StriderTol Bot change) |
||
| (One intermediate revision by the same user not shown) | |||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:- _ ____ __ _ __________ _-___-_____-____ - _ - | {{#Wiki_filter:- _ ____ __ _ __________ _-___-_____-____ - _ - | ||
e - | e - | ||
M mau. | M mau. | ||
O~ | O~ | ||
Log # TXX-91406 | Log # TXX-91406 2 | ||
File # 10010 | |||
~ | |||
Ref. # 10CFP50.55(a) | E Ref. # 10CFP50.55(a) | ||
TUG ECTRIC October 30, 1991 William J. Cahlit Jr. | TUG ECTRIC October 30, 1991 William J. Cahlit Jr. | ||
ag ra rmwe U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C, 20555 | ag ra rmwe U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C, 20555 | ||
| Line 31: | Line 31: | ||
==SUBJECT:== | ==SUBJECT:== | ||
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) | COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) | ||
DOCKET N05. 50 445 INSERVICE INSPECTION PROGRAM RELIEF REQUEST B-1 REQUEST FOR ADDITIONAL INFORMATION REF: | DOCKET N05. 50 445 INSERVICE INSPECTION PROGRAM RELIEF REQUEST B-1 REQUEST FOR ADDITIONAL INFORMATION REF: | ||
The referenced letter requested relief from the visual examination requirements (VT-2) for portions of the reactor coolant system during the system leakage test at the enu of the curreat refueling outage (IRF01). 1he | TV Electric letter from W. J. Cahill Jr. to U.S. NRC logged TXX-91377, dated October 16, 1991 Gentlemen: | ||
The referenced letter requested relief from the visual examination requirements (VT-2) for portions of the reactor coolant system during the system leakage test at the enu of the curreat refueling outage (IRF01). 1he requirements are found in Section XI of the ASHE Boiler and Pressure Code. | |||
Table IWB-2500 1, Category B-P. Item No. B15.50. | Table IWB-2500 1, Category B-P. Item No. B15.50. | ||
Subsequently, additional information was requested concerning the radiation levels and the man-kEM for this inspection. The radiation exposure in the areas to be VT 2 examined is approximately 1.9 REN. The total man-P.EH for the | Subsequently, additional information was requested concerning the radiation levels and the man-kEM for this inspection. | ||
The radiation exposure in the areas to be VT 2 examined is approximately 1.9 REN. | |||
The total man-P.EH for the VT-2 examination is approximately 12 man-REH. | |||
This includes accessing the i | |||
area to be inspected and actual performance of the inspection. | |||
In addition, we request that your approval be provided by November 20, 1991. | In addition, we request that your approval be provided by November 20, 1991. | ||
If there are any questions, please call Mr. C. E. Jensen at (214) 812 8826. | If there are any questions, please call Mr. C. E. Jensen at (214) 812 8826. | ||
Sincerely. | Sincerely. | ||
William J. Cahill | William J. Cahill Jr. | ||
n By: | n By: | ||
D. R. Woodlan Docket Licensing Hanager CEJ/gj | D. R. Woodlan Docket Licensing Hanager CEJ/gj ccr Hr. R. D. Hartin, Region IV O | ||
Resident Inspectors. CPSES (2) | |||
Mr. T. A. Bergman NRR 0 | Mr. T. A. Bergman NRR 0 | ||
ki | ki hhh h 43 400 N. Ouve Street LB. AI Dallas.Tcus 75201 o | ||
hhh h | PDh}} | ||
Latest revision as of 06:05, 26 May 2025
| ML20079L466 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 10/30/1991 |
| From: | Woodlan D TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-91406, NUDOCS 9111060304 | |
| Download: ML20079L466 (1) | |
Text
- _ ____ __ _ __________ _-___-_____-____ - _ -
e -
M mau.
O~
Log # TXX-91406 2
File # 10010
~
E Ref. # 10CFP50.55(a)
TUG ECTRIC October 30, 1991 William J. Cahlit Jr.
ag ra rmwe U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C, 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET N05. 50 445 INSERVICE INSPECTION PROGRAM RELIEF REQUEST B-1 REQUEST FOR ADDITIONAL INFORMATION REF:
TV Electric letter from W. J. Cahill Jr. to U.S. NRC logged TXX-91377, dated October 16, 1991 Gentlemen:
The referenced letter requested relief from the visual examination requirements (VT-2) for portions of the reactor coolant system during the system leakage test at the enu of the curreat refueling outage (IRF01). 1he requirements are found in Section XI of the ASHE Boiler and Pressure Code.
Table IWB-2500 1, Category B-P. Item No. B15.50.
Subsequently, additional information was requested concerning the radiation levels and the man-kEM for this inspection.
The radiation exposure in the areas to be VT 2 examined is approximately 1.9 REN.
The total man-P.EH for the VT-2 examination is approximately 12 man-REH.
This includes accessing the i
area to be inspected and actual performance of the inspection.
In addition, we request that your approval be provided by November 20, 1991.
If there are any questions, please call Mr. C. E. Jensen at (214) 812 8826.
Sincerely.
William J. Cahill Jr.
n By:
D. R. Woodlan Docket Licensing Hanager CEJ/gj ccr Hr. R. D. Hartin, Region IV O
Resident Inspectors. CPSES (2)
Mr. T. A. Bergman NRR 0
ki hhh h 43 400 N. Ouve Street LB. AI Dallas.Tcus 75201 o
PDh