NUREG-0472, Advises That 890825 Rev 1 to ODCM Acceptable.Future Changes to ODCM Should Be Implemented in Accordance W/Section 6.14 of Plant,Unit 1 Tech Specs: Difference between revisions
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# | {{Adams | ||
| number = ML20247C263 | |||
| issue date = 09/07/1989 | |||
| title = Advises That 890825 Rev 1 to ODCM Acceptable.Future Changes to ODCM Should Be Implemented in Accordance W/Section 6.14 of Plant,Unit 1 Tech Specs | |||
| author name = Grimes C | |||
| author affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | |||
| addressee name = Cahill W | |||
| addressee affiliation = TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) | |||
| docket = 05000445 | |||
| license number = | |||
| contact person = | |||
| case reference number = RTR-NUREG-0133, RTR-NUREG-0472, RTR-NUREG-133, RTR-NUREG-472 | |||
| document report number = GL-89-01, GL-89-1, NUDOCS 8909130291 | |||
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE | |||
| page count = 1 | |||
}} | |||
=Text= | |||
{{#Wiki_filter:_ | |||
Setpeinber 7 1989: | |||
0 | |||
;w fDockekNo.S0-445-t Mr.' William J.: Cahill, Jr. | |||
. Executive Vice President, Nuclear Texas Utilities Electric Company 400 North Olive Street, L~. B. 81 Dallas -Texas 75201 | |||
==Dear Mr. Cahill:== | |||
==SUBJECT:== | |||
REVISION 1 0F.0FFSITE DOSE CALCULATION MANUAL FOR COMANCHE PEAK STEAM ELECTRIC STATION Your {{letter dated|date=August 25, 1989|text=letter dated August 25,1989}} (TXX-89595) requested the' staff to review Revision 1 to:the Comanche Peak Offsite Dose Calculation Manual (0DCM) and- | |||
-inform you as to its acceptability. | |||
The staff has reviewed both Part I, " Radiological Effluent Controis" and. | |||
Part II, " Calculational Methodologies" of the subject document. Part I in-corporates completely, in accordance with Generic Letter.89-01, the procedural details of the Radiological Effluent Technical Specifications (RETS) required-by the NRC staff's model RETS for pressurized water reartors (PWRs), NUREG-0472, Revision 2, February 1,1980, and its most recent draft ;pdate. Part II uses l | |||
documented and approved methods that are consistent w' i the methodology and guidelines in NUREG-0133 for a reference document.. The staff, therefore, finds the ODCM to be acceptable. Future changes to this ODCM should be implemented | |||
.in accordance with Section 6.14 of the Comanche Peak,-Unit 1 Technical Specifi-cations. | |||
Should you have any questions on the staff's review of the ODCM, please contact either of our project managers, Melinda Malloy at (301)492-0738 or Mel Fields-at(301)492-0765. | |||
Sincerely, Christopher I. Grimes, Director Comanche Peak Project Division Office of Nuclear Reactor Regulation cc: 'See next page DISTRIBUTION Jockett11e(50945)ft JHWilson TEssig OGC 1 | |||
NRC PDR RWarnick JLee ACRS(10) | |||
Local PDR JLyons JCalvo | |||
( | |||
ADSP Reading MMalloy REmch CPPD Reading MFields RGiardina | |||
/# | |||
DCrutchfield CVandenburgh JPartlow kf TQuay FCongel Edordan q | |||
CGrimes LCunningham B | |||
PVD:NRR CP AD:CPP RIB hRPB:NRR D:CPPD:N, CIGrimes gWMeinke M4 alloy:cm M | |||
ds JHWils 09/h89 0 [ /89 09/(,/ | |||
-j 09/g /89 09/1/89 890?130291 800907' PDR ADOCK 05000445 A | |||
PDC | |||
-}} | |||
Latest revision as of 12:08, 22 May 2025
| ML20247C263 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak |
| Issue date: | 09/07/1989 |
| From: | Charemagne Grimes Office of Nuclear Reactor Regulation |
| To: | William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| References | |
| RTR-NUREG-0133, RTR-NUREG-0472, RTR-NUREG-133, RTR-NUREG-472 GL-89-01, GL-89-1, NUDOCS 8909130291 | |
| Download: ML20247C263 (1) | |
Text
_
Setpeinber 7 1989:
0
- w fDockekNo.S0-445-t Mr.' William J.
- Cahill, Jr.
. Executive Vice President, Nuclear Texas Utilities Electric Company 400 North Olive Street, L~. B. 81 Dallas -Texas 75201
Dear Mr. Cahill:
SUBJECT:
REVISION 1 0F.0FFSITE DOSE CALCULATION MANUAL FOR COMANCHE PEAK STEAM ELECTRIC STATION Your letter dated August 25,1989 (TXX-89595) requested the' staff to review Revision 1 to:the Comanche Peak Offsite Dose Calculation Manual (0DCM) and-
-inform you as to its acceptability.
The staff has reviewed both Part I, " Radiological Effluent Controis" and.
Part II, " Calculational Methodologies" of the subject document. Part I in-corporates completely, in accordance with Generic Letter.89-01, the procedural details of the Radiological Effluent Technical Specifications (RETS) required-by the NRC staff's model RETS for pressurized water reartors (PWRs), NUREG-0472, Revision 2, February 1,1980, and its most recent draft ;pdate. Part II uses l
documented and approved methods that are consistent w' i the methodology and guidelines in NUREG-0133 for a reference document.. The staff, therefore, finds the ODCM to be acceptable. Future changes to this ODCM should be implemented
.in accordance with Section 6.14 of the Comanche Peak,-Unit 1 Technical Specifi-cations.
Should you have any questions on the staff's review of the ODCM, please contact either of our project managers, Melinda Malloy at (301)492-0738 or Mel Fields-at(301)492-0765.
Sincerely, Christopher I. Grimes, Director Comanche Peak Project Division Office of Nuclear Reactor Regulation cc: 'See next page DISTRIBUTION Jockett11e(50945)ft JHWilson TEssig OGC 1
NRC PDR RWarnick JLee ACRS(10)
Local PDR JLyons JCalvo
(
ADSP Reading MMalloy REmch CPPD Reading MFields RGiardina
/#
DCrutchfield CVandenburgh JPartlow kf TQuay FCongel Edordan q
CGrimes LCunningham B
PVD:NRR CP AD:CPP RIB hRPB:NRR D:CPPD:N, CIGrimes gWMeinke M4 alloy:cm M
ds JHWils 09/h89 0 [ /89 09/(,/
-j 09/g /89 09/1/89 890?130291 800907' PDR ADOCK 05000445 A
-