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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#REDIRECT [[NUREG-0473, Forwards Draft,Rev 3 to NUREG-0472, Std Radiological Effluent Controls for Pwrs, Containing Draft Guidance for Radiological Effluent Tech Specs/Odcm Commitments,Per Generic Ltr 89-01]]
{{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

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
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

PDC

-