Letter Sequence Other |
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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
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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
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'0G Docket No. W 136, g%, IO8/g -Q
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A00921 N',x Mr. Boyce H. Grier, Director
'g Region I tu Office of Inspection and Enforcement U. S. Nuclear Regulatory Ccemission 631 Park Avenue King of Prussia, PA 19406
References:
(1)
B. H. Grier letter to W. G. Counsil, dated March 13, 1980, transmitting I&E Bulletin No. 80-06.
(2)
W. G. Counsil letter to B. H. Grier, dated June 13, 1980.
(3)
W. G. Counsil letter to B. H. Grier, dated October 20, 1980.
(4)
W. G. Counsil letter to B. H. Grier, dated February 13, 1981.
Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 I&E Bulletin No. 80 Engineered Safety Features Reset Control In Reference (1), the NRC Staff requested that Northeast Uuclear Energy Company (UNECO) investigate concerns related to the reset logic of engineered safety feature (ESF) components.
NNECO responded to the Reference (1) concerns in Reference (2), which included a listing of the ESF components whose reset logic did not conform to the recommendations delineated in Reference (1). Upon subsequent review of these IEF components, NNECO determined that the reset logic associated with certain components did not require modifications. These items are described in Reference (3), as supplemented by Reference (4), together with justification for their deletion from the Reference (2) listing.
The purpose of this correspondence is to provide the NRC Staff with additional information supplementary to that of Reference (4) which substantiates the Reference (3) conclusions.
81040 " [
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.-h-Ite=s 132 and 136 Iov Pressure Safety Injection (LPSI) pu=ps F k2A and P k2R are secured upon receipt of a Su=p Recirculation Actuat,L2 Sigmal (SRAS). Reset of a SPJLS vill result in the restart of the LPSI pu=ps only if a Safety Injeccion Actuation Signal (SIAS) is still present.
Operation of these co=ponents following reset of the SEAS is described in Reference (h). The conclusions and sup',crting. justification for the deletion of these co=ponents frc= the Peferance (2) listing, provided in References (3) and (4), re=ain valid.
Ite=s 180 and 187 It was reported in Reference (4) tha*. the Stea= Generator Feedvater Isolation Valves, F/-5k19 and El-5420, close upon receipt of a Main Stes= Isolation Signal (MSIS).
It was also reported that, upon reset of a MSIS, these valves vould reopen.
In actuality, these valves vill re=ain closed due to the differential pressure that vill exist across the valve upon loss of feedvater associated with a =ain stes isolation signal. The operation of the stea=
generator feedvater isolation valves is described below for clarification.
Upon receipt of the MSIS, the air supply solenoids to the operators of valves El-5419 and h'/-5h20 close and the vent solenoids open, venting the air operators permiting the sving check, steam generator feedvater isolation valves to close.
Reset of the MSIS closes the vent solenoids and re-applies air to the operators. As was stated above, however, the differential pressure across the valve that vill exist following a loss of =ain feedvater on MSIS vill prevent it frc= reopening.
As was discussed in Reference (h), the potential for '.he reopening of these va'.ves following a MSIS will be of no operational concern. ICTICO =aintains this position and the infor=ation presented above supports this conclusion.
- 4e trust you find this infor=ation satisfac+e / to clarify Reference (k).
Very truly yours, NORT5.ZAST NUCLEAR INIRGY COMPANY W
ii. G. **ounsil Senior Vice President AA- #
a
'4. F. Fee Ex<:cutive Vice President 8
e
