Letter Sequence Approval |
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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 ML19322E3811980-03-0505 March 1980 Responds to IE Bulletin 80-04 Re Analysis of PWR Main Steam Line Break W/Continued Feedwater Addition.Details of Control Grade Automatic Initiation of Auxiliary Feedwater Scheme Are Being Finalized.Necessity of Installation Is Questionable 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 ML20238E2381982-04-0505 April 1982 PWR Main Steam Line Break W/Continued Feedwater Addl Northwest Nuclear Energy Co Millstone Unit 2. Request for Addl Info 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 ML20244B9101982-05-20020 May 1982 Forwards Request for Addl Info Necessary to Complete NRC Review of Licensee 820125 & 0305 Responses to IE Bulletin 80-04, Analysis of PWR Main Steam Line Break W/Continued Feedwater Addition. Response Due in 45 Days.W/O Encl Project stage: RAI ML20053C3161982-05-20020 May 1982 Forwards Request for Addl Info Necessary to Complete NRC Review of Licensee 820125 & 0305 Responses to IE Bulletin 80-04, Analysis of PWR Main Steam Line Break W/Continued Feedwater Addition. Response Due in 45 Days.W/O Encl Project stage: RAI A02509, Responds to 820520 Request for Addl Info Re IE Bulletin 80-04, Main Steam Line Break W/Continued Feedwater Addition. No Damage Would Be Sustained If Pumps Ran for 30 Minutes Under Calculated Conditions1982-07-0606 July 1982 Responds to 820520 Request for Addl Info Re IE Bulletin 80-04, Main Steam Line Break W/Continued Feedwater Addition. No Damage Would Be Sustained If Pumps Ran for 30 Minutes Under Calculated Conditions Project stage: Request ML20062E2771982-07-22022 July 1982 Forwards Safety Evaluation of Util Analysis of Main Steam Line Break W/Continued Feedwater Addition,Submitted Per IE Bulletin 80-04.Analysis Acceptable Project stage: Approval ML20027D2541982-10-0707 October 1982 Forwards Safety Evaluation of Util 800125 & 820706 Responses to IE Bulletin 80-04 Re Resolution of Main Steam Line Break W/Continued Feedwater Addition.Util Analysis Acceptable. Issue Closed Project stage: Approval 1981-02-13
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NUCLEAR REGULATORY COMMISSION y
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March 19, 1981 Docket No. 50-336 Mr. W. G. Counsil, Vice President Nuclear Engineering & Operations Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06101
Dear Mr. Counsil:
By letter dated February 19, 1981, you provided information to document (1) the results of a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> endurance test of the A auxiliary feedwater (AFW) pump and (2) your intentions regarding compliance with our requirement to automate the start of the steam-driven AP4 pump. Your letter was in response to the requirements as set forth in our letter of January 14, 1981 and earlier correspondence dated October 22, 1979.
Each of these items will be addressed separately.
Item (1)
Based on our review of the submitted data, we conclude that an appropriate operating test of the APd pump A was completed on February 6,1981. This item, additional short-term recommendation No. 2 of our October 22, 1979 letter, is therefore, satisfactorily, resolved.
Item (2)
Long-Term Recommendations GL-3 from NUREG-0635 and our October 22, 1979 letter stated:
"At least one APd system punp and its associated flow path and essential instrumentation should automatically initiate APdS flow and be capable of being independent of any alternating current pcwer source for at least two hours. Conversion of direct power to alternating current is acceptable."
After extensive review of the justification for this requirement and the infornation you have supplied including the new data presented in your February 19, 1981 letter, we have concluded that only a small increase in postulated plant safety would result from automating the initiation of the steam-driven AFW pump at Millstone, Unit No. 2.
Therefore, we find that a relaxation of Long-Term' Recommendation GL-3 for this facility is appropriate at this time. This relaxation isgd -
based on the following considerations.
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The availability of two 100 percent of rated capacity, fu W 4
e independent electric-driven APd pumps that satisfy the spleh $
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failure criterion.
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- e The steam turbine-driven AFW pump will be modified to be completely independent of all AC power requirements by January 1,1982.
e Upon loss of off-site power with a resultant reactor trip and loss of both main feedwater and AFW flow, the steam generator " dry-out time" (time to loss of decay heat removal capability) is greater than 45 minutes.
The current emergency operating procedure; utilized during a station e
blackout explicitly direct the operator to manually initiate and confirm AFW flow to each steam generator from the steam turbine-driven pump.
This letter completes our review of the short-term, additional short-term and long-term recommendations presented in our October 2,1979 letter.
The detailed review of the safety grade instrumentation system required to automatically initiate the auxiliary feedwater system will be issued at a later time.
Since-'ly, A /"';
%bN obert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing -
cc: See next page i
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Northeast Nuclear Energy Company cc:
William H. Cuddy, Esquire Mr. Jchn Shediosky Day, Berry & Howard Resident Inspector / Millstone Counselors at Law c/o U.S.N.R.C.
One Constitution Plaza P. O. Drawer KK Hartford, Connecticut 06103 Niantic, CT 06357 Anthony Z. Roisman Mr. Charles Brinkman Natural Resources Defense Council Manager - Washington Nuclear 91715th Street, N.W.
Operations Washington, D. C.
20005 C-E Power Systens Combustion Engineering, Inc.
Mr. Lawrence Bettencourt, First Selectman 4853 Cordell Aven., Suite A-1 Town of Waterford Bethesda, MD 20014 Hall of Records - 200 Boston Post Road Waterford, Connecticut 06385 Northeast Nuclear Energy Corpany ATTN: Superintendent Millstone Plant Connecticut Energy Agency Post Office Box 128 ATTN: Assistant Director, Research Waterford, Connecticut 06385 and Policy Development Department of Planning and Energy Waterford Public Library Policy Rope Ferry Road, Route 156 20 Grand Street Waterford, Connecticut 06385 Hartford, CT 06106 Director, Criteria and Standards Division Office of Radiation Progracs (ANR-460)
U.S. Environmental Protection Agency Washington, D. C.
20460 U. S. Environmental Protection Agnecy Region I Office ATTN: EIS COORDINATOR John F. Kennedy Federal Building Boston, Massachusetts 02203 Northeast Utilities Service Corpany ATTN: Mr. James R. Hf amelwright Nuclear Engineering and Operations P. O. Box 270 Hartford, Connecticut 06101
.