Letter Sequence Other |
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Results
Other: A01024, Forwards Info Re Five Addl TMI-2 Related Requirements Applying to Operating Reactors Per 800507 Request.Integrated Assessment of Collective Impact of All Requirements Should Be Conducted, A02589, Forwards Addl Info Re safety-related ECCS Tank Outages, Provided Verbally on 821220 in Response to NUREG-0737, Item II.K.3.17, A03501, Requests Addl Time to Provide Info Re 6-inch Containment Purge & Vent Valve Operability.Info Will Be Provided by 831026, ML19340E921, ML20004B640, ML20008E564, ML20008F134, ML20054E184, ML20076A987, ML20078N847
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MONTHYEARML20076A9871979-04-27027 April 1979
Forwards Proposed Revision to Tech Specs to Allow Unlimited Containment Purges.Revisions Deal W/Containment Isolation Valves
Project stage: Other
A01024, Forwards Info Re Five Addl TMI-2 Related Requirements Applying to Operating Reactors Per 800507 Request.Integrated Assessment of Collective Impact of All Requirements Should Be Conducted1980-06-10010 June 1980
Forwards Info Re Five Addl TMI-2 Related Requirements Applying to Operating Reactors Per 800507 Request.Integrated Assessment of Collective Impact of All Requirements Should Be Conducted
Project stage: Other
ML19340E9211980-12-31031 December 1980
Forwards Rept on post-TMI Requirements in Response to NUREG-0737 & NRC
Project stage: Other
ML20008E5641981-02-27027 February 1981
Provides Justification for Min Containment Pressure Used to Initiate Containment Isolation for Facility,Per NRC 801231 Request Re NUREG-0737.Present Containment Isolation Setpoint Is Adequate & No Reduction in Setpoint Is Warranted
Project stage: Other
ML20008F1341981-03-0404 March 1981
Forwards ECCS Outage Rept for Facilities for 1980,in Response to NUREG-0737,Item II.K.3.17.No Sys or Tech Spec Mods Are Required
Project stage: Other
ML20004B6401981-05-20020 May 1981
Advises That No Mods Will Be Made to TMI Action Plan Item II.E.4.2 Re Containment Isolation Dependability.Signals Used for Containment Isolation Are Redundant & Diverse & Adequate to Ensure Safe Operation
Project stage: Other
A01845, Forwards Info Re NRC Orders Confirming Licensee Commitments on post-TMI Related Issues.Issues Have Been Addressed.If NRC Does Not Allow Util to Reserve Request for Hearing,Ltr Should Be Treated as Hearing Request1981-08-10010 August 1981
Forwards Info Re NRC Orders Confirming Licensee Commitments on post-TMI Related Issues.Issues Have Been Addressed.If NRC Does Not Allow Util to Reserve Request for Hearing,Ltr Should Be Treated as Hearing Request
Project stage: Request
ML20054E1841982-04-16016 April 1982
Forwards Responses to Generic Ltr 82-05 Re post-TMI Requirements Implementation.Continued Safe Operation Assured W/Existing Implementation Status
Project stage: Other
A02589, Forwards Addl Info Re safety-related ECCS Tank Outages, Provided Verbally on 821220 in Response to NUREG-0737, Item II.K.3.171982-12-29029 December 1982
Forwards Addl Info Re safety-related ECCS Tank Outages, Provided Verbally on 821220 in Response to NUREG-0737, Item II.K.3.17
Project stage: Other
A03501, Requests Addl Time to Provide Info Re 6-inch Containment Purge & Vent Valve Operability.Info Will Be Provided by 8310261983-10-12012 October 1983
Requests Addl Time to Provide Info Re 6-inch Containment Purge & Vent Valve Operability.Info Will Be Provided by 831026
Project stage: Other
ML20078N8471983-10-27027 October 1983
Forwards Response to NRC 830902 Comments on Unresolved Items Re Containment Purge/Vent Review.No Addl Tech Specs or Equipment Mods Warranted.Operability Requirement Met W/Compliance W/Tmi Item II.E.4.2
Project stage: Other
A03992, Requests Informal Appeal Meeting W/Nrc to Review Requested Mod of Hydrogen Purge Valves to Close on High Radiation Signal,Per Generic Ltr 84-08 & NUREG-0737,Item II.E.4.2.71984-05-15015 May 1984
Requests Informal Appeal Meeting W/Nrc to Review Requested Mod of Hydrogen Purge Valves to Close on High Radiation Signal,Per Generic Ltr 84-08 & NUREG-0737,Item II.E.4.2.7
Project stage: Meeting
1981-05-20
[Table View] |
Text
1*
f[SR MGg
o, UNITED STATES 2
g NUCLEAR REGULATORY COMMISSION O
E WASHINGTON, D. C. 20555 o
NOV I S 1979 MEMORANDUM FOR:
R. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors FROM:
G. Lainas, Chief Plant Systems Branch Division of Operating Reactors
SUBJECT:
MILLSTONE 2 - CONTAINMENT PURGE OVERRIDE OF CONTAINMENT ISOLATION (TAC 10819)
Plant Systems Branch has identified the enclosed additional infor-mation as being required in order that we can complete our evaluation of the electrical override / bypass aspects of the containment isolation matter.
G. Lainas, Chief Plant Systems Branch Division of Operating Reactors Enclosure :
As stated
Contact:
R. Scholl, X27162 cc w/ enclosure:
D. Eisenhut W. Gammill G. Lainas D. Tondi E. Conner P. Shemanski V. Panciera W. Russell E. Reeves E. Adensam R. Scholl 162d129
/63 g
7912190
... r Attachment A ELECTRICAL OVERRIDE / BYPASS DESIGN CRITERIA 1.
The overriding of one type of safety actuation signal (e.g.,
radiation) should not cause the blocking of any other type of safety actuation signal (e.g., pressure) to the isolation valves.
2.
Sufficient physical features (e.g., key lock switches) should be provided to facilitate adequate administrative controls.
3.
The system-level annunciation of the overridden status should be provided for every safety system impacted when an override is active.
4.
Diverse signals should be provided to initiate isolation of the containment ventilation system. Specifically, containment high radiation, safety injection actuation, and containment high pressure should automatically initiate CVI.
5.
The instrumentation and control systems provided to initiate CVI should be designed and qualified as safety-grade equipment.
6.
The overriding or resetting of the isolation actuation signal should not cause the automatic reopening of any isolation /
purge valve.
..e
'7620 M
