Letter Sequence Other |
|---|
|
Results
Other: A00921, Forwards Addl Response to IE Bulletin 80-06, Engineered Safety Feature Reset Controls. Reset Logic Associated W/Certain Components Did Not Require Mods.Items & Justification for Deletions Described, A01060, Responds to IE Bulletin 80-06, Engineered Safety Feature (ESF) Reset Controls. Three Facilities Will Have Completed Mods Per IE Bulletin 80-06 by 810101.List of Equipment & Status of Criteria Encl, A01488, Responds to NRC Requesting Auxiliary Feedwater Pump Endurance Test & Compliance W/Requirement to Automate Steam Driven Auxiliary Feedwater Pump.Test Confirmed Pump Vibrations Did Not Exceed Allowable Limits, ML17208B070, ML19211A900, ML19260B517, ML19305D956, ML19309B223, ML19343D005, ML20005A873, ML20054E184
|
MONTHYEARML19260B5111979-12-0606 December 1979 Forwards Proposed Automatic Initiation Scheme for Auxiliary Feedwater Sys, in Response to NRC Request for Specific Design Details & Demonstration of Compliance W/Hr Denton Project stage: Request ML19253C9351979-12-0606 December 1979 Forwards Rept Re Proposed Automatic Initiation of Auxiliary Feedwater Sys in Response to NRC Request for Sepcific Design Details & for Demonstration of Compliance W/Nrc to All Operating Nuclear Power Plants Project stage: Request ML19211A9001979-12-17017 December 1979 Forwards Design Drawings Re Automatic Initiation of Auxiliary Feedwater,In Response to NRC Request.W/O Encl. List of Drawings Encl Project stage: Other ML17208B0701979-12-18018 December 1979 Provides Info on Compliance W/Tmi Lessons Learned Task Force short-term Item Re Auxiliary Feedwater Sys Flow Indication, in Response to NRC 791211 Request.Util Installing Single Control Grade Flow Indication Channel Per Feedline Project stage: Other ML19260B5171979-12-31031 December 1979 Proposed Automatic Initiation Scheme for Auxiliary Feedwater Sys Project stage: Other ML19309B2231980-03-31031 March 1980 Proposed Revisions to Tech Specs 3.7.1.2 & 4.7.1.2,adding Surveillance Requirement for Auxiliary Feedwater Flow Test After Cold Shutdown Exceeding One Month Project stage: Other ML19309B1741980-03-31031 March 1980 Application to Amend License DPR-65,in Response to Concerns Expressed in NRC .Revisions Add Surveillance Requirement for Auxiliary Feedwater Flow Test After Cold Shutdown Exceeding One Month.Affidavit Encl Project stage: Request ML19305D9561980-04-11011 April 1980 Discusses Problems W/Implementation of Lessons Learned Task Force Recommendation Re Automatic Initiation of Auxiliary Feedwaters Sys.Requests NRC Concurrence W/Plan for Implementing Requirement During 1980 Refueling Outage Project stage: Other ML19323F2551980-05-20020 May 1980 Tech Spec Change Request for Tables 3.3-3,3.3-4,3.3-5 & 4.3-2,for Engineered Safety Features Actuation Sys Instrumentation,Trip Values,Response Times & Surveillance Requirements Project stage: Request A00803, Application to Amend License DPR-65,submitted as Proposed Revision to Tech Specs,In Response to NRC . Summarizes Status of Implementation of Automatic Initiation of Auxiliary Feedwater.One Pump Sufficient1980-05-20020 May 1980 Application to Amend License DPR-65,submitted as Proposed Revision to Tech Specs,In Response to NRC . Summarizes Status of Implementation of Automatic Initiation of Auxiliary Feedwater.One Pump Sufficient Project stage: Request A01060, Responds to IE Bulletin 80-06, Engineered Safety Feature (ESF) Reset Controls. Three Facilities Will Have Completed Mods Per IE Bulletin 80-06 by 810101.List of Equipment & Status of Criteria Encl1980-06-13013 June 1980 Responds to IE Bulletin 80-06, Engineered Safety Feature (ESF) Reset Controls. Three Facilities Will Have Completed Mods Per IE Bulletin 80-06 by 810101.List of Equipment & Status of Criteria Encl Project stage: Other A00921, Forwards Addl Response to IE Bulletin 80-06, Engineered Safety Feature Reset Controls. Reset Logic Associated W/Certain Components Did Not Require Mods.Items & Justification for Deletions Described1981-02-13013 February 1981 Forwards Addl Response to IE Bulletin 80-06, Engineered Safety Feature Reset Controls. Reset Logic Associated W/Certain Components Did Not Require Mods.Items & Justification for Deletions Described Project stage: Other A01488, Responds to NRC Requesting Auxiliary Feedwater Pump Endurance Test & Compliance W/Requirement to Automate Steam Driven Auxiliary Feedwater Pump.Test Confirmed Pump Vibrations Did Not Exceed Allowable Limits1981-02-19019 February 1981 Responds to NRC Requesting Auxiliary Feedwater Pump Endurance Test & Compliance W/Requirement to Automate Steam Driven Auxiliary Feedwater Pump.Test Confirmed Pump Vibrations Did Not Exceed Allowable Limits Project stage: Other ML19347D4851981-03-19019 March 1981 Discusses Review of Util Providing Info Re 48-h Auxiliary Feedwater Pump Endurance Test & Compliance W/Nrc Requirement to Automate Start of steam-driven Pump.Item Re Pump Test Resolved Project stage: Approval ML19343D0051981-03-20020 March 1981 Suppls 810213 Response to IE Bulletin 80-06, Engineered Safety Feature (ESF) Reset Controls. Low Pressure Safety Injection Pumps P-42A & B Are Secured Upon Receipt of Sump Recirculation Actuation Signal Project stage: Other ML20005A8731981-06-26026 June 1981 Informs That Control Board Mounting Hardware for Auxiliary Feedwater Flow Indicators Will Not Arrive Prior to Required 810701 Inservice Date,Per NUREG-0737,Item II.E.1.2.Vendor Failed to Order Equipment.Foxboro Co Encl Project stage: Other 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 1980-05-20
[Table View] |
Text
a ff gggg General Offices o Selden Street, Berlin, Connecticut we au,urmion ae aw a uwar P o. BOX 270
]
nw,wnee n e mu+o uwa' HARTFORD. CONNECTICUT 06101
- .7:~","'C "~'
awww L
L J
- ':4;":"JJl"C" June 26, 1981 6
4 Docket No. 50-336 F \\.
/
h 1 J L,1
,,,U 6
A01379 p
2 JUL 011981 * --
Director of Nuclear Reactor Regulation "l,
Wise M A3^* Y h
g Attn:
Mr. Robert A. Clark, Chief D
Operating Reactors Branch #3 qD y
U. S. Nuclear Regulatory Commission 0
Washington, D.C.
20555
Reference:
(1)
W. G. Counsil letter to D. G. Eisenhut. dated December 31, 1980.
Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 Auxiliary Feedwater Flow Indication Item II.E.1.2 described in NUREG-0737 requires that safety grade auxiliary feedwater flow indication be provided at Millstone Unit No. 2 by July 1, 1981. In Reference (1), Northeast Nuclear Energy Company (NNECO) docu-mented its intention to comply with the required in-service date in NUREG-0737 for Item II.E.1.2.
Due to an oversight on the part of the equipment vendor, NNECO will not receive control board mounting hardware for the auxiliary feedwater flow indicators in time to support the. required in-service date of July 1, 1981. This is documented in the attached letter from the vendor to NNECO.
Upon receipt of the subject hardware, NNECO will expedite the installation of the auxiliary feedwater flow indicators. The revised in-service date for this system is conservatively estimated to be August 1, 1981. NNECO has determined that the slight deviation from the schedule provided for in NUREG-0737 for this system is acceptable as the automatic initiation of the auxiliary feedwater system at Millstone Unit No. 2 is operational and provides increased assurance that adequate feedwater will be available to remove decay heat. Current auxiliary feedwater flow indication, al-though not scfety-grade, will provide adequato indication of auxiliary feedwater flow until the safety-grade system installation is complete.
181970:10 [/6' 6
/
~..
- -:q t,
we trust you find this information satisfactory and concur in the revised
~
in-service date for the auxiliary feedwater flow indicators.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY
[
/.
/
/
/
.. f ( A) 9.c {
W. G. Counsil Senior Vice President r
W
--wr.h
-.. +,,
--w
=
,a
8
'^
l
~
Foxboro, MA 0203s U.SA The Foxboro Company
<ei73 s43-87s0 June 18, 1981 Northeast Nuclear Energy Co.
P. O. Box 270 Hartford, Connecticut 06101 Attention: Bob McCarthy
Reference:
P.O. No. 526665 Foxboro S.O. No. 80N-42911 Gentlemen:
Due to an oversight, we neglected to order the Model N-2AX+H096 Housing and the N-2AX+RB01 Retaining Bar which is necessary to mount the Model N-257 on your order. The material has now been ordered and will be shipped on July 1, 1981.
We regret any inconvenience this may cause.
Very truly yours, THE FOXBORO COMPANY 0)L Joan Weir Power Systems Engineering cas cc: Northeast Nuclear Energy Co.
i P. O. Box 128 l
Waterford, Connecticut 06385 Attn: Jeff Cataudella ammmuummer
.