Letter Sequence Request |
|---|
|
|
MONTHYEARML19257D8081980-01-31031 January 1980
Forwards Proposed Mods to Improve post-accident Monitoring Capability.Mods Adequately Address Lessons Learned Task Force Category a Design Review Items & Description of Mods Contained in Section 2.1.8 of NRC
Project stage: Other
ML19340E1291980-12-30030 December 1980
Responds to NUREG-0737.Util Working W/Oh State Univ on Feasibility Evaluation of long-term Program to Phase Out Need for Shift Technical Advisor.Commitment Supersedes All Previous Commitments
Project stage: Other
ML20041C1731982-02-19019 February 1982
Notifies of Delays Re Implementation of NUREG-0737 Items II.F.1.2 & II.B.3.Station Vent Stack Monitor Mods to Be Performed After Outage.Reactor post-accident Sampling Sys Operational,Pending Delivery of Operator Panel
Project stage: Other
ML20065H9941982-09-29029 September 1982
Advises That Schedule for Responding to NUREG-0737,Item II.B.3, Post-Accident Sampling Sys, Will Be Provided by Mar 1983,in Response to 820721 Request
Project stage: Other
ML20069L5741983-04-25025 April 1983
Forwards Info for post-implementation Review of NUREG-0737, Item II.B.3, Post-Accident Sampling Sys, Per Util .Certain Requested Info Will Not Be Available Until After Completion Date of 831231
Project stage: Other
ML20115A2601984-07-19019 July 1984
Requests That Encl Request for Addl Info Be Transmitted to Util.Info Needed to Continue Review of plant-specific Emergency Operator Guidelines Associated W/Procedures Generation Package
Project stage: Request
ML20094Q2721984-08-14014 August 1984
Forwards Addl Info Concerning NUREG-0737,Item II.B.3 Re post-accident Sampling,Per 840719 Request.Rexnord Model 340 Portable Oxygen Monitor Used to Determine Dissolved Oxygen in Reactor Coolant Sample
Project stage: Other
1982-09-29
[Table View] |
Text
"
y.,.,
.. muq'o,,
UNITED STATES 2,
%g g
NUCLEAR REGULATORY COMMISSION
]
g*
p WASHINGTON. D. C. 20555
,/
July 19,1984 D ckst No. S0-346 MEMORANDUM FOR: John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing FROM:
Dennis L. Ziemann, Chief Procedures and Systems Review Branch Division of Human Factors Safety
SUBJECT:
DAVIS BESSE 1 - PGP-EOP REQUEST FOR ADDITIONAL INFORMATION Please transmit the enclosed request for additional information to the Toledo Edison Company so that we may continue our review of the plant-specific Emergency Operator Guidelines associated with the Davis Besse Procedures Generation Package.
b i
ld*k b W
Dennis L. Ziemann Chief Procedures and Systems Review Branch Division of Human Factors Safety
Enclosure:
As stated cc w/ enclosure:
W.Lycut,~
AI,0,e,A,gazf r mR
-=--
- e-
7
/
+ /
REQUEST FOR ADDITIONAL INFORMATION
/
DAVIS BESSE Justify the adequacy of Davis Besse plant-specific technical guidelines by referencing the NRC-approved B&W guideline as applicable, and identifying and justifying safety-significant differences between Davis Besse guidelines and the referenced guidelines.
4 I
l l
. -.