Letter Sequence Other |
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Results
Other: A01061, Forwards Info Re Design Basis Transient & Accident Conditions Providing Basis for Auxiliary Feedwater Sys Flow Requirements,In Response to NRC 791022 Request.Based on Analyses,Auxiliary Feedwater Sys Complies W/Section 1.4, B10116, Advises of Discrepancy Between Delays Cited in Util 800520 Analysis Re Use of Two Electrically Driven Auxiliary Feedwater Pumps in Automatic Initiation Scheme.Multiple Conservatisms Justify Validity of Analysis, ML19210E670, ML19211A900, ML19211C160, ML19253C587, ML19257C081, ML19257C288, ML19257D549, ML19260B517, ML19305A972, ML19305D956, ML19309B223, ML19322E381, ML19338C766, ML20125D098
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MONTHYEARML19256E2921979-10-22022 October 1979 Fowards Generic Request for Addl Info & Requirements for Auxiliary Feedwater Sys Project stage: RAI ML19210E6701979-11-28028 November 1979 Responds to NRC 791018,22 & 1121 Requests Re short- & long- Term Recommendations for Auxiliary Feedwater Sys Requirements Project stage: Other ML19253C5871979-11-30030 November 1979 Forwards Calculations Re Automatic Initiation of Auxiliary Feedwater & Supporting Statement That Longer Time Is Available for Haddem Neck Steam Generator Dryout than for Millstone-2 Project stage: Other ML19260B5111979-12-0606 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 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 ML19211C1601979-12-21021 December 1979 Requests Tech Specs for Auxiliary Feedwater Sys Mods & Revision of Normal & Emergency Operating Procedures. Sample Tech Spec Pages Encl Project stage: Other ML20125D0981979-12-27027 December 1979 Responds to to Hendrie Re Concerns About Requirement for Automatically Initiated Auxiliary Feedwater Sys at Facilities.Requests Analysis of Effect of Failure to Isolate Feedwater Flow to Affected Steam Generator Project stage: Other ML19260B5171979-12-31031 December 1979 Proposed Automatic Initiation Scheme for Auxiliary Feedwater Sys Project stage: Other ML19257C0811980-01-0303 January 1980 Forwards Summary of Bulletins & Orders Task Force 791218-19 Audit of Small Break LOCA Emergency Procedure & Operator Retraining.List of Exit Interview Attendees & List of Instrument Power Supplies Encl Project stage: Other ML19257C2881980-01-17017 January 1980 Submits Results of Review of Operating Records of 48-h Endurance Test on Auxiliary Feedwater Pumps,In Response to short-term Recommendations of NRC 791011 & 22 Ltrs.Intent of Recommendation Fulfilled Project stage: Other ML19257D5491980-01-25025 January 1980 Forwards Info Re Automatic Initiation of Auxiliary Feedwater.No Conclusion Reached Re Acceptability of Implementation Project stage: Other ML19273D1251980-02-14014 February 1980 Forwards Licensee Accident Analysis Re Main Steam Line Break Inside Containment.Requests Safety Evaluation.Licensee Plans to Submit Auxiliary Feedwater Sys auto-initiation Sys Which Delays Auxiliary Feedwater Flow for Three Minutes Project stage: Approval 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 ML19305A9721980-03-10010 March 1980 Advises That Util Response to NRC 791022 Request Re Auxiliary Feedwater Sys Flow Design Info Is Scheduled for Submittal on or About 800616 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 ML19275E7271980-05-0909 May 1980 Suppl to Safety Evaluation Supporting Licensee 800125 Response.Peak Containment Pressure Will Remain Below Design Pressure Even W/Addition of Auxiliary Feedwater at run-out Flow Project stage: Approval ML19275E7241980-05-0909 May 1980 Forwards Supplemental Safety Evaluation Supporting Licensee 800125 Response.Peak Containment Pressure Will Remain Below Design Pressure Even W/Addition of Auxiliary Feedwater at Run Out Flow Project stage: Approval 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 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 A01061, Forwards Info Re Design Basis Transient & Accident Conditions Providing Basis for Auxiliary Feedwater Sys Flow Requirements,In Response to NRC 791022 Request.Based on Analyses,Auxiliary Feedwater Sys Complies W/Section 1.41980-06-16016 June 1980 Forwards Info Re Design Basis Transient & Accident Conditions Providing Basis for Auxiliary Feedwater Sys Flow Requirements,In Response to NRC 791022 Request.Based on Analyses,Auxiliary Feedwater Sys Complies W/Section 1.4 Project stage: Other B10061, Application for Amend to License DPR-65,incorporating Proposed Revisions to Tech Specs Required to Support Plant Operation During Cycle 4 Reload1980-08-29029 August 1980 Application for Amend to License DPR-65,incorporating Proposed Revisions to Tech Specs Required to Support Plant Operation During Cycle 4 Reload Project stage: Request ML19338C7661980-08-29029 August 1980 Proposed Revisions to Tech Specs Required to Support Plant Operation During Cycle 4 Reload Project stage: Other ML19338D1421980-09-0202 September 1980 Requests Class III Fee for Review of 800520 Application for Proposed Tech Spec Changes Re Automatic Initiation of Auxiliary Feedwater Sys.Application Involves Consideration of Single Safety Issue Project stage: Approval B10116, Advises of Discrepancy Between Delays Cited in Util 800520 Analysis Re Use of Two Electrically Driven Auxiliary Feedwater Pumps in Automatic Initiation Scheme.Multiple Conservatisms Justify Validity of Analysis1980-10-31031 October 1980 Advises of Discrepancy Between Delays Cited in Util 800520 Analysis Re Use of Two Electrically Driven Auxiliary Feedwater Pumps in Automatic Initiation Scheme.Multiple Conservatisms Justify Validity of Analysis Project stage: Other B10127, Advises of Error in Sgn 111 Code Used for Feedline Break Analysis Submitted 800616 in Response to NRC 791022 Request for Addl Info Re Auxiliary Feedwater Sys Flow Requirements. Forwards Reanalysis Using Sgn 111 Code1980-11-20020 November 1980 Advises of Error in Sgn 111 Code Used for Feedline Break Analysis Submitted 800616 in Response to NRC 791022 Request for Addl Info Re Auxiliary Feedwater Sys Flow Requirements. Forwards Reanalysis Using Sgn 111 Code Project stage: Request 1980-10-31
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NORTHEAST IFFILFFIES 5
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Nm"ro*nE cONNECUt'JT 06101 "l"::L':::1l. ? ~'
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t a '".l::TC. ::L ' "r January 17, 1980 Docket Nos. 50-213 50-336 Darrell G. Eisenhut, Acting Director Division of Operating Reactors Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Ref erences:
(1)
D. G. Eisenhut letter to D. C. Switzer dated October 11, 1979.
(2)
D. G. Eisenhut letter to W. G. Counsil dated October 22, 1979.
(3)
W. G. Counsil letter to D. G. Eiscahut dated December 4,1979.
(4)
W. G. Counsil letter to D. G. Eisenhut dated November 28, 1979.
(5)
W. C. Counsil letter to R. Reid dated August 22, 1979.
Gentlemen:
Haddam Neck Plant Millstone Nuclear Power Station, Unit No. 2 Auxiliary Feedwater Systems In References (1) and (2), Connecticut Yankee Atomic Power Company (CYAPCO) and Northeast Nuclear Energy Company (NNECO) were requested to review the Haddam Neck Plant and Millstone Unit No. 2 against the applicable requirements of Enclosure (1) of References (1) and (2) to determine the current degree of conformance.
Itemized responses to t i requests were provided in References (3) and (4) for CYAPCO and n. SCO, respectively.
One of the additional short-term recommendations of References (1) and (2) was that each licensee perform a 72-hour endurance test on all AFW pumps, if such a test or continuous period of operation has not been accomplished to date.
In subsequent telephonc discussions, the Staf f advised that the recommended minimum duration of the test was revised to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, rather than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
In References (3) and (4), CYAPCO and NNECO advised that operating records and history were being reviewed, such that the appropriateness of such tests could be determined. This review has been completed, and the conclusions reached are as follows.
1809.330 8001250 dII7 P
e Millstone Unit No. 2 For Millstone Unit No. 2, NNECO retains run-time logs for plant equipment for only one calendar year.
These records were reviewed for the calendar year 1979 and maximum periods of operation were identified as tollows:
Pump Date Hours (1)
"A" Auxiliary Feedwater 5/18 - 5/19 27.5 (2)
"B" Auxiliary Feedwater 5/18 - 5/19 43.5 (3) Terry Turbine 6/15 - 6/19 96.0 Typical plant evolutions requiring the use of the auxiliary feedwater pumps were described in Reference (5).
In general, the electrically driven pumps are the preferred source to support these evolutions. Although documentation regarding motor-driven pump operation prior to 1979 cannot be provided, their use over the life of the plant has been extensive.
Therefore, NNECO has concluded that the intent of this recommendation has been fulfilled, and that supplemental endurance tests would be superfluous.
Haddam Neck Plant Documentation analogous to that described above for Millstone Unit No. 2 is not available at the Haddam Neck Plant, regarding the two steam-driven auxiliary feedwater pumps.
Plant evolutions requiring the use of these pumps is similar to that discussed in Reference (5). A typical startup from a refueling shutdown would include rod-drop tests and low power physics testing. This evolution involves the operation of the auxiliary feedwater pumps for a period of four-to-five days.
Pwsp operation is normally evenly divided between the two such that the endurance capability of each pump is well established.
Routine surveillance tests are also performed monthly.
During the life of the facility, these pumps have been operated for extended periods without identification of any deleterious ef fects attributable in long-term operation. Therefore, CYAPCO has concluded that the intent of this recommendation has been fulfilled, and that supplemental endurance tests would be superfluous.
We trust you find the above information responsive to your request.
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY NORTHEAST NUCLEAR ENERGY COMPANY o
a W. G. Mounsil Vice President By:
W. F. Fee Vice President 1809 331