Letter Sequence Request |
|---|
|
Results
Other: ML17268A104, ML19347F660, ML20003B230, ML20010G846, ML20010G862, ML20032A736, ML20063F261, ML20065N032, ML20067D230, ML20079Q273, ML20079Q282, ML20133E265
|
MONTHYEARML19257A5131979-12-28028 December 1979
Forwards Addl Response to ,Per Joint Nrc/B&W Owners Group 790913 Meeting.Addresses Noncondensible Gas Discussion & Small Break & Power Operated Relief Valve stuck-open Discussion
Project stage: Meeting
ML20003B2301981-01-30030 January 1981
Informs That Certain Mods Will Be Made to Existing Small Break LOCA Model,In Response to NRC .Revised Model Documentation Will Be Provided by 820301
Project stage: Other
ML20003B6721981-02-16016 February 1981
Submits Addl Comments on NUREG-0737,Items II.B.2 & II.K.3.30.Design Review Completed Re Plant Shielding for Spaces Outside Containment That May Be Used in post-accident Operations
Project stage: Request
ML19347F6601981-05-19019 May 1981
Responds to RW Reid Re Small Break LOCA Model to Predict Small Break Behavior.Discusses L3-1 & S-07-10D Test Prediction Comparisons.Earlier Pretest Predictions Being Reviewed & Results to Be Submitted by 810615
Project stage: Other
ML17268A1041981-05-31031 May 1981
B&W Post-Test Evaluation of Loft Test L3-1
Project stage: Other
ML20010G8621981-06-0909 June 1981
B&W Post-Test Analysis for Semiscale Test S-07-10D
Project stage: Other
ML20010G8461981-09-15015 September 1981
Forwards B&W Post-Test Analysis for Semiscale Test S-07-10D & B&W Post-Test Evaluation of Loft Test L3-1, in Response to NRC Re Small Break LOCA Model to Predict Small Break Behavior
Project stage: Other
ML20032A7361981-10-23023 October 1981
Requests That Buchholz to Eisenhut Be Added to Facility Dockets as Final Response to NUREG-0737,Item II.K.3.30 Re Small Break LOCA
Project stage: Other
ML20052A0611982-03-25025 March 1982
Summarizes NRC Views Resulting from 811217 Meeting W/B&W Owners Group Re Small Break LOCA Analysis Model & Provides Addl Info for Planning Verification Program. Model Verification Endorsed
Project stage: Meeting
ML20062M1431982-08-13013 August 1982
Responds to Requesting Schedule for Submittal of Supplemental ECCS Calculations Using Cladding Models of NUREG-0630.Calculations Will Be Submitted by 830301
Project stage: Supplement
ML20063F2611982-08-25025 August 1982
Discusses Program for Resolution of NUREG-0737,Item II.K.3.30, Revised Small Break LOCA Methods to Show Compliance w/10CFR50,App K. B&W Will Forward Description of Gerda Test Program
Project stage: Other
ML20065A8891982-09-0909 September 1982
Submits Details of Cooperative Evaluation Program,Requested at 820720 Meeting Re NUREG-0737,Item II.K.3.30, Revised Small Break LOCA Methods to Show Compliance w/10CFR50,App K. Program Will Lead to Development of Research Priorities
Project stage: Meeting
ML20065N0321982-10-19019 October 1982
Responds to Requesting Implementation Schedule for Mods to ECCS Evaluation Models.Mods Will Be Undertaken as Extension of NUREG-0737,Item II.K.3.31.Schedule Will Be Provided 60 Days After NRC Approval of Item II.K.3.30
Project stage: Other
ML20067D2301982-12-0707 December 1982
Endorses B&W Topical Repts BAW-10154P, B&W Small Break LOCA ECCS Evaluation Model & BAW-10092P,Revision 3, CRAFT-2, in Effort to Complete Small Break LOCA Methods Program Response to NUREG-0737,Item II.K.3.30
Project stage: Other
ML20023B8711983-04-0505 April 1983
Public Version of Temporary Mod Request T-7104 to Emergency Plan Implementing Procedure Ei 1300.07, Technical Support Ctr Activation. Rev 27 to Index Encl
Project stage: Request
ML20079Q2821983-05-0606 May 1983
Bounding Analytical Assessment of NUREG-0630 on LOCA & Operating Kw/Ft Limits
Project stage: Other
ML20079Q2731983-05-0606 May 1983
Forwards Bounding Analytical Assessment of NUREG-0630 on LOCA & Operating Kw/Ft Limits, Per
Project stage: Other
ML20133E2651985-07-0303 July 1985
Topical Rept Evaluation of BAW-10092P,Rev 3 & BAW-10154 Re Small Break LOCA Evaluation Model CRAFT2 (Rev 3).CRAFT2 in Compliance W/Evaluation Criteria of 10CFR50,App K
Project stage: Other
1982-10-19
[Table View] |
Submits Addl Comments on NUREG-0737,Items II.B.2 & II.K.3.30.Design Review Completed Re Plant Shielding for Spaces Outside Containment That May Be Used in post-accident Operations| ML20003B672 |
| Person / Time |
|---|
| Site: |
Hatch  |
|---|
| Issue date: |
02/16/1981 |
|---|
| From: |
Widner W
GEORGIA POWER CO. |
|---|
| To: |
Office of Nuclear Reactor Regulation |
|---|
| References |
|---|
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.2, TASK-2.K.3, TASK-2.K.3.30, TASK-TM NUDOCS 8102250148 |
| Download: ML20003B672 (2) |
|
Similar Documents at Hatch |
|---|
|
Text
5 Gect;a oweCo
~ 230 Dar'*'ree Sues
' ~ Post C"a 80 454F Aanta Gjerg a 3C30$~~
Te ecrone 404 5224060 1
b
!.3 W. A. W I[ner February 16, 1981 GeorgiaPower Ye?e",*,9?le'.,[c?n*"*' " ' *"
rne sourrm eac s, stem Director of Nuclear Reactor Regulation U.
S.
Nuclear Regulatory Commission Washington, D.
C.
20555 NRC 00CKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I.
HATCH NUCLEAR PLANTS UNITS 1, 2 ADDITIONAL COMMENTS ON NUREG-0737 ITEMS GENTLEMEN:
Georgia Power Compuny hereby submits additional informational comments concerning the status of compliance with the requirements of Item II.B.2 and Item II.K.3.30 of NUREG-0737.
A design review of plant shielding for spaces outside containment which may be used in post-accident coerations has been completed and a
detailed design for implementation of shielding modifications has been developed and is available for review.
These actions complete all actions for Item II.B.2 required to date.
One technical deviation from the criteria of NUREG-0737 was employed in the review and design of clant shielding.
As noted in our letters of January 25, December 15, and December 31, 1980, the source term used in Containment spray, core spray, HPCI liquid, RCIC liquid, and RHR-LPCI systems took credit for dilution of the reactor coolant system mass with the suppression pool mass.
This dilution reflects the expected condition of reactor coolant and liquids recirculated by the above systems.
In a November 19, 1980, letter to the NRC, Georgia Power Company requested that questions regarding the scope and schedule of Item II.K.3.30 of NUREG-0737 be directed to General Electric directly for resolution.
It is now our understanding, based upon discussion with members of the NRC staff, that this request is denied.
We therefore now endorse the letter from R.
H.
Buchholz to D.
G.
Eisenhut describing the scope and schedule of the BWR program to address this item (GE letter MFN-202-80 dated November 18, 1980).
Future NRC correspondence on this item should be directed to Georgia Power Company with copies to the Manager of BWR Systems Licensing of General Electric, Mr.
R.
H.
Buchholz.
Submittals described in Mr. Buchholz's letter of November 18, 1980, will be reviewed and submitted on the Hatch docket tc meet the requirements of this item.
L, g
\\
810'2250lW f
i.
Georgia Power d Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission February 16, 1981 Page Two Should you have questions with regard to these
- comments, please contact this office.
Very truly yours, 7Wi. ?s:Le W.
A. Widner WEB /mb Sworn to and subscribed before me this 16th day of February, 1981.
Notary Pubic Georgia. State at urge
- i / /,
/. / --/l / /f (,.
My Commason Eeres Sept. 20,1983 j
Notary Public xc:
M..Manry R.
F. Rogers, III