Letter Sequence Request |
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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, B12620, Proposed Tech Specs,Revising Page 6-19 to Add or Reclose to Requirements for Submittal of Annual Repts, B12630, Proposed Tech Specs,Adding New Surveillance Requirement Re Control Room Habitability, ML19340E921, ML20049J167, ML20235S064, ML20236H316
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MONTHYEARML19256A1121978-10-27027 October 1978 Application for Amend to License DPR-35,changing Tech Specs to Accomodate New Steamline Break Protection Sys Scheduled for Installation in Spring of 1979.Fee Paid Project stage: Request ML20071G1291978-12-14014 December 1978 Forwards Addl Info Re Lic Amend Appl Covering Eval of Low Feedwater Flow Reactor Trip Setpoint Change Project stage: Other ML19263C8021979-02-0505 February 1979 Lists Individual Fee Classes for 781027 Application for Tech Spec Changes.Requests Submittal of Addl $13,500 Fee. Any Overcharges Will Be Refunded Project stage: Other ML19276E2751979-03-0707 March 1979 Forwards Addl Info Requested at 790223 Meeting Re Proposed Steam Break Protection Sys Project stage: Meeting ML19270F9971979-03-12012 March 1979 Summary of 790223 Meeting W/Westinghouse & Duquesne Light Re Steamline Break Protection Sys.W/Supporting Documentation Project stage: Meeting ML19241B4271979-07-13013 July 1979 Tech Spec Change Requests 42 & 47 Re Mod to ECCS Project stage: Other ML19241B4191979-07-13013 July 1979 Forwards Tech Spec Change Requests 42 & 47 Re Amend to App a of DPR-72.Change Is Required Prior to Startup After Completion of Planned ECCS Mod,Which Could Be Accomplished as Early as 790722 Project stage: Other ML19274G1021979-07-31031 July 1979 Forwards Request for Addl Info to Util Proposed Steam Break Protection Sys & N-1 Loop Operation Project stage: RAI ML19208B5691979-08-21021 August 1979 Forwards Safety Evaluation Re Electrical,Instrumentation & Control Aspects of Deletion of Reactor Trip on Turbine Trip Below 50% Power Project stage: Approval ML19254D2721979-10-18018 October 1979 Forwards Addl Info Re Proposed Steam Break Protection Sys Per Tech Spec Change Request 35.Proposed Tech Spec Re Maint of Required Shutdown Margin & Revised Reactivity Control Sys Tech Specs Encl Project stage: Other ML19259D6001979-10-18018 October 1979 Summary of 791009 Meeting W/Util Re Proposed Steamline Break Protection Project stage: Meeting ML19309A8581980-03-28028 March 1980 Forwards Documents Re Investigation Into Extended Outages at Facility.Documents Include Trial Staff Statement Before PA Public Util Commission,Consumer Advocate Statement & CN Dunn Testimony Project stage: Request ML19309H2151980-04-15015 April 1980 Notification of 800422 Meeting W/Util in Bethesda,Md to Discuss & Review Decay Heat Exchanger Sys Integrity & Operation Project stage: Request IR 05000302/19800181980-05-0707 May 1980 IE Insp Rept 50-302/80-18 on 800331-0411.No Noncompliance Noted.Major Areas Inspected:Previous Insp Findings,Fuel Receipt,Refueling Activities,Maint Activities & IE Bulletin 79-01B Project stage: Request IR 05000334/19800081980-05-0707 May 1980 IE Insp Rept 50-334/80-08 on 800324-28.No Noncompliance Noted.Major Areas Inspected:Qa Program Review,Qa/Qc Administrative Design Change & Mod Control,Measurement & Test & Previous Insp Items Project stage: Request ML19310A4261980-06-0909 June 1980 Responds to & Schedule for Implementation of TMI-2-related Requirements.Discusses Shift Manning,Scope & Criteria for Licensing Exam,Procedures for Feedback of Operating Experience & Control Room Habitability 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 IR 05000412/19800061980-07-0303 July 1980 IE Insp Rept 50-412/80-06 on 800602-06.Noncompliance Noted: Failure to Return Used or Damaged Welding Electrodes to Issue Station & Failure to Provide Adequate Protection for Equipment in Temporary Storage Project stage: Request ML19321A6951980-07-21021 July 1980 Forwards Schedule for Commitments to TMI-2 Related Requirements,Per NRC 800507 Request.Affidavit Encl Project stage: Other ML19330B7541980-07-31031 July 1980 Informs of Intentions to Withdraw Commitment to Adopt Guidance of IE Circular 80-02,due to Wording of IE Circular 80-02 & Application of Circular Re Work Situations Project stage: Other ML19343A3821980-09-15015 September 1980 Tech Specs 3/4 3-38,requesting Changes Re Model License Conditions,Emergency Feedwater Initiation & Flow Monitoring, Diverse Containment Isolation & Emergency Power Supply to Pressurizer Heaters Project stage: Other ML19343A3791980-09-15015 September 1980 Application to Amend App a to Ol,Changing Aspects of NUREG-0578 Including Model License Conditions & Emergency Feedwater Initiation & Flow Monitoring.Affidavit & Certificate of Svc Encl Project stage: Request ML19339A5091980-10-24024 October 1980 Withdraws Tech Specs Change Request 47,implementing Items Contained in NRC 790516 Confirmatory Order.Util Considers Specs Requested in Eisenhut & Provided in Change Request 64,Revision 1,as Representing Latest Position Project stage: Other ML19339A5981980-10-29029 October 1980 Advises of Status Re Shift Staffing,In Response to Interim Criteria in NRC Project stage: Other ML19339B2141980-10-31031 October 1980 Advises That Util Has Not Made Plans to Conduct Any Qualification Tests During Next 2 Yrs.Nrc Will Be Notified in Event of Decision to Conduct Tests Project stage: Request ML19345E1321980-12-17017 December 1980 Responds to Re Confirmation of Commitment to Meet Implementation Dates Contained in NUREG-0737.Requests Extension for Proposed Mods Re Auto Trip of Reactor Coolant Pumps Project stage: Other ML19347C7391980-12-31031 December 1980 Forwards Nonproprietary & Proprietary Versions of Response to NUREG-0737. Proprietary Version Available in Central Files Only Project stage: Other ML19340E9211980-12-31031 December 1980 Forwards Rept on post-TMI Requirements in Response to NUREG-0737 & NRC 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 ML20049H5531982-02-24024 February 1982 Provides Info on Item II.K.3.5 Re Automatic Trip of Reactor Coolant Pumps During Loca,Per NUREG-0737 Requirements. Status Submitted in Has Not Changed Project stage: Other ML20049J1671982-03-0808 March 1982 Ack Receipt of 801231 Response to TMI Action Plan Item II.K.3.3, Reporting Relief Valve & Safety Valve Failures & Challenges. No Further Review Planned.Item Resolved Project stage: Other ML20042B9261982-03-16016 March 1982 Forwards Request for Addl Info for Review of TMI Action Items 2.A.2.1,upgrading Senior Reactor Operator & Reactor Operator Training & II.B.4,training for Mitigating Core Damage Project stage: RAI ML20050C5071982-03-24024 March 1982 Ack Commitment in to Meet Reporting Requirement Provided in NRC Re Relief & Safety Valve Failures.Info Missing from 1981 Annual Rept.Requests That Rept Be Updated W/Errata Sheet to Correct Discrepancy Project stage: Other ML20052A9481982-04-23023 April 1982 Requests Addl Info Re TMI Action Plan Item II.K.3.3, Reporting Relief Valve & Safety Valve Failures.Response within 30 Days Requested Project stage: Other ML20052G1951982-05-10010 May 1982 Informs of No Relief or Safety Valve Failures or Challenges During Apr-Dec 1980 in Response to 820423 Request for Documentation & Commitment to NUREG-0737,Item II.K.3.3, Reporting Relief & Safety Valve Failures & Challenges Project stage: Request ML20053D7211982-05-27027 May 1982 Forwards Westinghouse Transmitting SAR for Deletion of Reactor Trip Following Turbine Trip Below 50% Power.Review Requested Against NUREG-0737,Item II.K.3.10 Concerns Project stage: Other ML20066D3001982-11-0303 November 1982 Informs That Since Unit 1 Anticipatory Trip Mod Is Enveloped by Unit 2 Analysis Basis,Analysis May Be Applied to Unit 1 Per Requirements of TMI Item II.K.3.10, Proposed Anticipatory Trip Mod Project stage: Other ML20084C5841984-04-24024 April 1984 Discusses 830808 Program Plan Rept for Detailed Control Room Design Review Containing Section Entitled, Mgt & Staffing, Outlining Min Qualification for Team Members.Resumes Encl Project stage: Request A06182, Responds to 861029 Request for util-proposed Tech Spec Changes Re Reporting of Safety Valve & Relief Valve Failure & Challenges,Control Room Habitability & Secondary Water Chemistry.Schedule for Submittal of Amend Requests Encl1986-12-10010 December 1986 Responds to 861029 Request for util-proposed Tech Spec Changes Re Reporting of Safety Valve & Relief Valve Failure & Challenges,Control Room Habitability & Secondary Water Chemistry.Schedule for Submittal of Amend Requests Encl Project stage: Request ML20235S0641987-07-14014 July 1987 Proposed Tech Specs,Adding Requirement That Annual Rept Submitted to NRC Must Include Documentation of All Failures & Challenges to Pressurizer PORV & Safety Valves Project stage: Other B12568, Application for Amend to License DPR-65,adding Requirement That Annual Rept Submitted to NRC Must Include Documentation of All Failures & Challenges to Pressurizer PORV or Safety Valve.Application Submitted Per 870615 Commitment.Fee Paid1987-07-14014 July 1987 Application for Amend to License DPR-65,adding Requirement That Annual Rept Submitted to NRC Must Include Documentation of All Failures & Challenges to Pressurizer PORV or Safety Valve.Application Submitted Per 870615 Commitment.Fee Paid Project stage: Request ML20236H3161987-07-31031 July 1987 Forwards Revised Page 6-19 to 870714 Proposed Tech Specs, Adding Requirement That Annual Rept Submitted to NRC Include Documentation of All Failures of & Challenges to Pressurizer PORVs & Safety Valves.Two Words, or Reclose Added Project stage: Other B12620, Proposed Tech Specs,Revising Page 6-19 to Add or Reclose to Requirements for Submittal of Annual Repts1987-07-31031 July 1987 Proposed Tech Specs,Revising Page 6-19 to Add or Reclose to Requirements for Submittal of Annual Repts Project stage: Other B12630, Proposed Tech Specs,Adding New Surveillance Requirement Re Control Room Habitability1987-08-0303 August 1987 Proposed Tech Specs,Adding New Surveillance Requirement Re Control Room Habitability Project stage: Other ML20236N0591987-08-0303 August 1987 Application for Amend to License DPR-65,adding New Surveillance Requirement Re Control Room Habitability.Fee Paid Project stage: Request 1980-06-09
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i NORTHEAST UTILITIES cenerei Orrices. seiden street, Beriin. connecticut 9
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HARTFORD, CONNECTICUT 06141-0270 l
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l August 3,1987
-J Docket No. 50-336 B12630 Re: 10CFR 50.90 U.S. "'uclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20535 Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 I
Proposed Change to Technical Specifications Control Room Habitability Pursuant to 10CFR50.90, Northeast Nuclear Energy Company (NNECO) hereby j
proposes to amend its Operating License DPR-65 by incorporating the attached l
changes into the Technical Specifications for Millstono Unit No. 2.
The proposed change, included as Attachment (1) to this letter, consists of a new f
Surveil!ance Requirement (Section 4.7.6.2.e.3) which is being added to 4
page 3/4 7-17. This new surveillance requirement snecif.ies that every 18 months (essentially each refueling outage) a test will be performed that demonstrates that, at a delta-pressure of 1/16" of water gauge, in-leakage of air into the l
control room js limited to lets thar,100 standard cubic feet per minute (scfm).
j This change is being proposed to support the control room ha'Oability,) evaluation performed for Millstone Unit No. 2. In a letter dated June 19,1985,u the NRC Staff issued Amendment No.100 to the operating license for Millstone Unit No. 2.
This amendment issued changes to the Technical Specifications that supported NNECO's evaluation of control room habitability in accordance with NUREG 0737, item II.D.3.4.
The NRC Staff Safety Evaluation, included in Reference (1), stated that an additional license amendment was necessary to include in the Technical Specifications a requirement to periodically verify the air in-leakage assumption made in NN CO's control room habitability analysis. In a letter dated December 10, 1986,(
NNECO committed to provide by August 3, 1987 a license amendment request to verify the ana'.ysis assumption. The license amendment request contained herein fulfills that commitment.
1 (1)
D. B. Osborne letter to J. F. Opeka, " Amendment No.100 to Facility l
Operating License No. DPR-65," dated June 19,1985.
(2)
E. J. Mroczka letter to.. C. Thadani, " Request for Additional Information, l
Reporting of SV and RV Failures and Challenges, Control Room Habitability, 3
Secondary Water Chemistry," dated December 10,1986.
' I 8708110357 870803
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i DR ADOCK 0500 6
U.S. Nuclear Regulatory Commission B12630/Page 2 August 3,1987 NNECO has reviewed the attached proposed change pursuant to 10CFR50.59 and has determined that it does not constitute an unreviewed safety question. The i
new Surveillance Requirement proposed herein provides an additional test.that ensures that a previously docketed analysis remains valid. with respect to all assumptions made. This proposed change does not increase the probability or
' l consequences of an accident previously analyzed nor create the potential for a new unanalyzed accident nor reduce the margin of safety as defined in the basis of any Technical Specification..The proposed change adds a.new Surveillance Requirement that helps to ensure that the current analysis for control room habitability remains valid.
i NNECO has reviewed the proposed change in accordance with 10CFR50.92 and has concluded that it involves no significant hazards consideration in that these changes would not:
1 1.
Involve a significant increase in the probability or consequences of an accident previously evaluated.
Since the proposed change provides an additional survelliance test not previously required, greater assurance of the continued validity of the control room habitability evaluation is ensured.
Therefore, there is no increase in the probability or ' consequences of an accident previously analyzed.
j 1
2.
Create the possibility of a new or different kind of accident from any 1
previously ar.alyzed. Again, due to the nature of this change as described above, no new accidents or malfunctions are created. This proposed change provides additional control and restriction over systems already in service at the plant.
)
l 3.
Involve a significant reduction in a margin of safety. As previously stated, this change will not adversely affect the margins of safety in existing specifications. This proposed change represents an addition to the Technicai l
l Specifications.
NNECO's conclusion that the three criteria of 10CFR50.92(c) are not compro-1 mised is supported by cur determination made pursuant to 10CFR50.59.
With respect to the proposed Technical Specification change, our review of the given examples in 51 FR 7750, March 6,1986, of amendments that are considered not likely to involve a significant hazards consideration has determined that example (ii), a change that constitutes an additional limitation, restriction, or l
l control not presently included in the Technical Specifications, is applicable. The l
proposed change institutes a new surveillance requirement which will help ensure the control room ventilation system performs as intended.
The Millstone Unit No. 2 Nuclear Review Board has reviewed and approved the attached proposed revisions and has concurred with the above determinations.
In accordance with 10CFR50.91(b), we are providing the State of Connecticut with a copy of this proposed amendment.
Pursuant to the requirements of 10CFR170.12(c), enclosed with this amendment request is the application fee of $150.
l l
4
U.S. Nuclear Regulatory Commission B12630/Page 3 August 3,1987 NNECO respectfully requests that this amendment be issued with an effective date corresponding to entrance into Mode 4 following -the upcoming refueling outage at Millstone Unit No. 2.
This outage is presently scheduled to begin in January 1988.. Compliance with the Limiting Condition for Operation (LCO 3.7.6,-
Control Room Emergency Ventilation System), based on the proposed new Surveillance Requirement, cannot be verified until the test is performed. This new surveillance test is to be conducted during refueling outa<;es, with the first test to be performed during the upcoming refueling outage. In order to perform this test, NNECO must procure some equipment and prepare some systems.
l Therefore, NNECO is hereby requesting that this proposed Technical Specification j
change not be effective until af ter the refueling outage to allow the necessary preparations for and the conduct of the initial test.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY
/YA 2A./
E. 3.'M rKczka
{}
Senioriice President l
I cc:
Kevin McCarthy Director, Radiation Control Unit Department of Environmental Protection Hartford, CT 06116 cc:
W. T. Russell, Region I Administrator D. H. Jaffe, NRC Project Manager, Millstone Unit No. 2 T. Rebelowski, Resident inspector, Millstone Unit Nos. I and 2 STATE OF CONNECTICUT)
) ss. Berlin i
COUNTY OF HARTFORD )
Then personally appeared before me, E. 3. Mroczka, who being duly sworn, did state that he is Senior Vice President of Northeast Nuclear Energy Company, a Licensee herein, that he is authorized to execute and file the foregoing information in the name and on behalf of the Licensees herein, and that.the statements contained in said information are true and correct to the best of his knowledge and belief.
LAAAnd 0 &>tte Motary Puby My Commission Expires March 31,1988 l