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Category:GRANTS OF EXEMPTION FROM & EXTENSION TO NRC REQUIREME
MONTHYEARML20195J4791998-11-19019 November 1998 Exemption from Certain Requirements of 10CFR50.54(w) & 10CFR140.11 Re Reduction in Amount of Insurance Required for Facility ML20238F2111998-08-28028 August 1998 Exemption from Provision of 10CFR50.54(q) That Require Emergency Plans to Meet Standard of 10CFR50.47(b) & Requirements of App E to Part 50 ML20236S1901998-07-15015 July 1998 Exemption from Requirements of 10CFR73.55, Requirements for Physical Protection of Licensed Activities in Nuclear Power Reactors Against Radiological Sabotage ML20245J0081989-08-14014 August 1989 Exemption Permitting one-time Extension of Test Period for Type a Test from 870927,or Later,Until Next Refueling Outage & for Type B & C Tests from 870718,or Later,Until Next Refueling Outage ML20155G1031988-10-0303 October 1988 Temporary Exemption from Schedular Requirements of Property Insurance Rule 10CFR50.54(w)(5)(i),effective 881004 ML20237C1371987-11-27027 November 1987 Exemption from 10CFR50,App R Requirements Re Fire Protection Features in Primary Auxiliary,Svc & Turbine Bldgs & Emergency Lighting in Event of Fire ML20236D2351987-10-15015 October 1987 Exemption from Requirements of App J to 10CFR50,Paragraph III.A.3 to Allow Use of Mass Point Method as Provided in Ansi/Ans 56.8-1981 to Calculate Containment Leakage ML20235S4931987-09-29029 September 1987 Exemption from Requirements of 10CFR50,App J,For All Penetrations Identified in Table 2 of Exemption Package for Period of Two Refueling Outages Following 1987 Outage ML20212M8811986-08-25025 August 1986 Exemption from Schedular Requirements of 10CFR50.48 for Mod to Switchgear Room & Related Plant Areas,To Assure Adequate Level of Fire Protection,Subj to Licensee Submittal of Implementation Plan by 860930 & Subsequent Bimonthly Repts ML20203M5321986-04-28028 April 1986 Exemption from Requirements of GDC 35 & Interim Acceptance Criteria for Valves RH-MOV-784 & SI-MOV-24 for Cycle 14 Operation ML20137R0011985-11-22022 November 1985 Exemption from 10CFR50.71(e)(3)(ii),extending Date to 870630 for Util to File Updated Sar.Exemption Contingent Upon Util Ability to Meet Proposed Identified Guidelines ML20204K0481985-04-11011 April 1985 Exemption from 10CFR50.71(e) for Submittal of Updated Facility Description & Safety Analysis 1998-08-28
[Table view] Category:LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
MONTHYEARML20195H1911999-06-15015 June 1999 Application of Montaup Electric Co & New England Power Co for Transfer of Licenses & Ownership Interests.Requests That Commission Consent to Two Indirect Transfers of Control & Direct Transfer CY-99-076, Comment Supporting Proposed Rules 10CFR1,2,4,7,9,15,16,76 & 110 Re Initiative to Implement New Document Mgt Sys That Would Permit Electronic Storage,Retrieval & on-line Ordering of Publicly Available NRC Official Records1999-05-20020 May 1999 Comment Supporting Proposed Rules 10CFR1,2,4,7,9,15,16,76 & 110 Re Initiative to Implement New Document Mgt Sys That Would Permit Electronic Storage,Retrieval & on-line Ordering of Publicly Available NRC Official Records ML20204B6631999-02-22022 February 1999 Comment on Recommended Improvements to Oversight Process for Nuclear Power Reactors.Forwards 5th Edition of Nuclear Lemons Assessment of America Worst Commerical Nuclear Power Plants ML20195J4791998-11-19019 November 1998 Exemption from Certain Requirements of 10CFR50.54(w) & 10CFR140.11 Re Reduction in Amount of Insurance Required for Facility ML20195E2361998-11-16016 November 1998 Director'S Decision 98-12,granting Petitioner Request to Investigate Licensee Proposal to Air Cool SFP & Denying Request to Suspend Operating License of Plant ML20154J9991998-09-11011 September 1998 Requests NRC Take Immediate Action to Revoke Util License to Operate Haddam Neck Nuclear Power Station Pursuant to 10CFR2.206 CY-98-139, Comment on Draft NUREG-1625, Proposed Standard TSs for Permanently Defueled Westinghouse Plants1998-09-0101 September 1998 Comment on Draft NUREG-1625, Proposed Standard TSs for Permanently Defueled Westinghouse Plants ML20238F2111998-08-28028 August 1998 Exemption from Provision of 10CFR50.54(q) That Require Emergency Plans to Meet Standard of 10CFR50.47(b) & Requirements of App E to Part 50 ML20236S1901998-07-15015 July 1998 Exemption from Requirements of 10CFR73.55, Requirements for Physical Protection of Licensed Activities in Nuclear Power Reactors Against Radiological Sabotage ML20216B5661998-03-31031 March 1998 Comment Supporting NRC Draft RG DG-1071, Std Format & Content for Post-Shutdown Decommissioning Activities Rept ML20217E9051998-03-13013 March 1998 Requests,Pursuant to 10CFR2.206,that NRC Take Immediate Action to Suspend CYAPCO License to Operate Connecticut Yankee Nuclear Power Station in Haddam Neck,Connecticut ML20199A1631997-10-28028 October 1997 Forwards Final Page of Exhibit 2,P Gunter Ltr to Commission on Behalf of Nirs Re Prs 10CFR2,50 & 51 Involving Immediate Recission of Current Decommissioning Rules,Conducting Site Specific Health Study & EA &/Or EIS ML20199A1351997-10-24024 October 1997 Comment Opposing Proposed Rules 10CFR2,50 & 51 Re Immediate Rescission of Current Decommissioning Rules & Provision for Hearing on Decommissioning Plan for Plant.W/Nirs & Affidavits of M Resnikoff,S Mangiagli & R Bassilakis DD-97-21, Partial Director'S Decision DD-97-21 Denying Request for Immediate Suspension or Revocation of Licenses & Granting Request for Investigation of Possible Matl Misrepresentations,In Response to 961125 & 1223 Petitions1997-09-12012 September 1997 Partial Director'S Decision DD-97-21 Denying Request for Immediate Suspension or Revocation of Licenses & Granting Request for Investigation of Possible Matl Misrepresentations,In Response to 961125 & 1223 Petitions DD-97-19, Partial Director'S Decision DD-97-19,deferring in Part & Denying in Part,Citizens Awareness Network & Nirs 970311 Petition to Commence Enforcement Action Against Util & Impose Civil Penalty1997-09-0303 September 1997 Partial Director'S Decision DD-97-19,deferring in Part & Denying in Part,Citizens Awareness Network & Nirs 970311 Petition to Commence Enforcement Action Against Util & Impose Civil Penalty ML20137P5481997-03-11011 March 1997 Petition Filed on Behalf of Citizens Awareness Network of Massachusetts,Connecticut & Vermont & Nirs to Modify License by Placing Certain Listed Conditions on License & Imposing Civil Penalty,Per 10CFR2.206 ML20137Q9171997-03-0303 March 1997 Constitutes Petition Filed on Behalf of AA Cizek,Per 10CFR2.206,to Modify Licenses Issued to Millstone & Connecticut Yankee by Placing Certain Conditions on OLs ML20134J5891997-01-15015 January 1997 Transcript of 970115 Public Meeting in Higganum,Ct.Pp 1-129. Supporting Documentation Encl ML20133E4651996-12-23023 December 1996 Amend to Citizens Awareness Network & Nirs Petition for Enforcement Per 10CFR2.206 to Revoke Northeast Utilities OL for Connecticut Nuclear Power Stations Due to Chronic, Systemic Mismanagement....* ML20133H1131996-11-25025 November 1996 Petition for Enforcement,Per 10CFR2.206,to Revoke Northeast Utils Operating Licenses for CT Nuclear Power Stations Due to Chronic,Systemic Mismanagement Resulting in Significant Violations of NRC Safety Regulations ML20134P0681996-11-14014 November 1996 Comment on Draft RG DG-1051, Monitoring Effectiveness of Maint at Npp ML20133G2791996-08-29029 August 1996 Transcript of 960829 Connecticut Public Television Broadcast of Citizens Regulatory Commission, Nuclear Safety Issues, Discussion W/Former Employee of Plant.Pp 1-59 ML20059F7761994-01-0303 January 1994 Comment on Proposed Rule 10CFR73 Re Proposal to Amend Its Physical Protection Regulations for Operating Nuclear Power Reactors by Modifying Design Basis Threat for Radiological Sabotage B14644, Comment on Proposed Rules 10CFR30,40,50,60,70 & 72 Re Whistleblower Protection for Nuclear Power Plant Employees.Supports Rules1993-10-14014 October 1993 Comment on Proposed Rules 10CFR30,40,50,60,70 & 72 Re Whistleblower Protection for Nuclear Power Plant Employees.Supports Rules B14346, Comment Supporting Draft RG DG-1020, Monitoring Effectiveness of Maint at Nuclear Power Plants1993-01-15015 January 1993 Comment Supporting Draft RG DG-1020, Monitoring Effectiveness of Maint at Nuclear Power Plants ML20059P0631990-10-15015 October 1990 Comment on Proposed Rules 10CFR2,50 & 54 Re Nuclear Power Plant License Renewal.Endorses Comments Submitted by NUMARC B13572, Comment Opposing Petition for Rulemaking PRM-50-55 Re Periodicity of Submissions of FSAR Revs1990-07-0202 July 1990 Comment Opposing Petition for Rulemaking PRM-50-55 Re Periodicity of Submissions of FSAR Revs B13567, Comment on Proposed Rule 10CFR55 Re Operators Licenses Mod for fitness-for-duty.Endorses NUMARC Position That Rule Challenges Licensed Operators Trustworthiness W/O Justification & Would Affect Morale of Licensed Operators1990-07-0202 July 1990 Comment on Proposed Rule 10CFR55 Re Operators Licenses Mod for fitness-for-duty.Endorses NUMARC Position That Rule Challenges Licensed Operators Trustworthiness W/O Justification & Would Affect Morale of Licensed Operators B13367, Comment on Proposed Rules 10CFR30,40,50,60,70,72 & 150 Re Preserving Free Flow of Info to Commission.Nrc Made Wise Choice to Not Impose Any Obligation on Private Parties to Include Affirmative Statement in Employment Agreements1989-09-20020 September 1989 Comment on Proposed Rules 10CFR30,40,50,60,70,72 & 150 Re Preserving Free Flow of Info to Commission.Nrc Made Wise Choice to Not Impose Any Obligation on Private Parties to Include Affirmative Statement in Employment Agreements ML20245J0081989-08-14014 August 1989 Exemption Permitting one-time Extension of Test Period for Type a Test from 870927,or Later,Until Next Refueling Outage & for Type B & C Tests from 870718,or Later,Until Next Refueling Outage ML20245G0721989-08-0303 August 1989 Comment on Draft Reg Guide, Assuring Availability of Funds for Decommissioning Nuclear Reactors. Recommends That NRC Recommendation on Trust Agreement Wording Be Deleted or NRC Should Grandfather Existing Trusts Such as for Plants ML20246K4801989-07-0505 July 1989 Comment Opposing Proposed Rule 10CFR50, Acceptance of Products Purchased for Use in Nuclear Power Plant Structures,Sys & Components ML20246N9471989-03-0808 March 1989 Comment on Proposed Rev 3 to Reg Guide 1.9 Re Selection Design,Qualification,Testing & Reliability of Diesel Generator Units Used as Onsite Electric Power Sys at Nuclear Power Plants B13113, Comment on Proposed Rev 3 to Reg Guide 1.9, Selection, Design,Qualification,Testing & Reliability of Diesel Generator Units.... Util Recommends Rule Be Revised to Incorporate Addl Flexibility in Considering Age of Diesel1989-03-0808 March 1989 Comment on Proposed Rev 3 to Reg Guide 1.9, Selection, Design,Qualification,Testing & Reliability of Diesel Generator Units.... Util Recommends Rule Be Revised to Incorporate Addl Flexibility in Considering Age of Diesel ML20236B4641989-03-0808 March 1989 Comments on Proposed Rev 3 to Reg Guide 1.9, Selection, Design,Qualification,Testing & Reliability of Diesel Generator Units Used as Onsite Electric Power Sys at Nuclear Power Plants. Reg Guide Does Not Provide Flexibility B13136, Comment Opposing Proposed Rule 10CFR50 Re Effectiveness of Maint Programs for Nuclear Power Plants.Proposed Rule on Maint Will Not Improve Maint in Plants Nor Improve Safety or Reliability of Plants.Proposed Rule Much Too Vague1989-02-27027 February 1989 Comment Opposing Proposed Rule 10CFR50 Re Effectiveness of Maint Programs for Nuclear Power Plants.Proposed Rule on Maint Will Not Improve Maint in Plants Nor Improve Safety or Reliability of Plants.Proposed Rule Much Too Vague ML20235N5471989-02-0909 February 1989 Undated Comment Opposing Proposed Rules 10CFR50 & 55 Re Education & Experience for Senior Reactor Operators & Supervisors at Nuclear Power Plants.Neither Alternative Acceptable or Needed ML20206M5321988-11-21021 November 1988 Comment Supporting Proposed Rule 10CFR26 Re fitness-for-duty Program ML20155G1031988-10-0303 October 1988 Temporary Exemption from Schedular Requirements of Property Insurance Rule 10CFR50.54(w)(5)(i),effective 881004 ML20196E5931988-06-22022 June 1988 Comment Supporting Proposed Rule 10CFR50 Re Emergency Planning & Preparedness Requirements for Nuclear Power Plant Fuel Loading & Initial Low Power Operations B12891, Comment Opposing Proposed Rule 10CFR50 Re Licensee Announcement of Inspector on Site1988-04-18018 April 1988 Comment Opposing Proposed Rule 10CFR50 Re Licensee Announcement of Inspector on Site ML20151A8881988-03-31031 March 1988 Comments Supporting Proposed Rule 10CFR50 Re Leakage Testing of Containment to Permit Use of Mass Point Method as Alternative Method for Calculating Containment Leakage Rates.Mass Point Method More Accurate for Calculating Rates B12870, Comment Supporting Proposed Rule 10CFR50 Re Leakage Testing of Containments to Permit Use of Mass Point Method as Alternative Method for Calculating Containment Leakage Rates1988-03-31031 March 1988 Comment Supporting Proposed Rule 10CFR50 Re Leakage Testing of Containments to Permit Use of Mass Point Method as Alternative Method for Calculating Containment Leakage Rates ML20147C3191988-01-0606 January 1988 Comment Opposing SRP Section 3.6.3 of NUREG-0800.Utils Endorse Comments by Nuclear Util Group on Equipment Qualification ML20237C1371987-11-27027 November 1987 Exemption from 10CFR50,App R Requirements Re Fire Protection Features in Primary Auxiliary,Svc & Turbine Bldgs & Emergency Lighting in Event of Fire ML20236D2351987-10-15015 October 1987 Exemption from Requirements of App J to 10CFR50,Paragraph III.A.3 to Allow Use of Mass Point Method as Provided in Ansi/Ans 56.8-1981 to Calculate Containment Leakage B12706, Comment Supporting Proposed Rule 10CFR50 Re Rev of Backfitting Process for Power Reactors1987-10-13013 October 1987 Comment Supporting Proposed Rule 10CFR50 Re Rev of Backfitting Process for Power Reactors ML20235S4931987-09-29029 September 1987 Exemption from Requirements of 10CFR50,App J,For All Penetrations Identified in Table 2 of Exemption Package for Period of Two Refueling Outages Following 1987 Outage ML20212M8811986-08-25025 August 1986 Exemption from Schedular Requirements of 10CFR50.48 for Mod to Switchgear Room & Related Plant Areas,To Assure Adequate Level of Fire Protection,Subj to Licensee Submittal of Implementation Plan by 860930 & Subsequent Bimonthly Repts ML20205F4181986-08-12012 August 1986 Correction to Commission 860702 Order Confirming Licensee Commitments on Emergency Response Capability 1999-06-15
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l 7590-01 i t
UNITED' STATES OF AMERICA I I
NUCLEAR REGULATORY COMMISSION J d
In the Matter of ~ )
CONNECTICUT. YANKEE ATOMIC Docket No. 50-213 POWER COMPANY. ) .
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Haddam Neck Plant )
'I EXEMPTION '
. I. t The Connecticut Yankee Atomic power Company (CYAPC0, the Licensee) is the holder.of Operating License No. DPR-61 which authorizes operation of the Haddam '
Neck Plant (the facility) at the steady-state power levels not in excess of 1825 megawatts thermal. The license provides, among other things, that the !
Haddam Neck Plant'is subject to all rules, regulations, and Orders of the i Conmission now'or hereafter in effect. !
The plant is a single-unit pressurized water reactor at the licensee's i
site located in Middlesex County, Connecticut.
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i II.
The Code of Federal Regulations,10 CFR 50.54(o), specifies that primary reactor containments for vater-cooled power reactors shall comply with Appendix J, " Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors." Paragraph III.A.3 of Appendix J incorporates by reference the American National Standard (ANSI) N45.4-1972, " Leakage Rate Testing of Containment Structures for Nuclear Reactors." This standard requires that 8710280001 B71015 PDR P
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1 containment leakage: calculations-for Containment Integrated Leakage Rate Tests. .l
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. (CILRTs). be performed usin[:. either the Point-to-Point method or the Total Time method. !'
A'more recent standard, ANSI /ANS 56.8-1981, " Containment System Leakage- }
Testing," which was' intended to replace ANSI N45.4-1972, specifies the use of-the Mass Point method to the exclusion of ~the two older methods. l A' proposed '!
revision to Appendix J, which has.been published for public comment (51 FR 39538, dated October 29,.1986), refers to a proposed Regulatory Guide (MS 021-5, Cetober 1986), which endorses, with certain exceptions, the ANSI /ANS 56.8-1981 standard.
Pending approval of the revision to Appendix J, which would permit the Mass Point
' analysis, licensees'who wish to use the Mass Point technique must submit an ap' plication for. exemption from the requirement that Appendix J test calculations j for CILRTs will conform with ANSI N45.4-1972. 1 l l III.
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By letter datad July:10, 1987, the licensee requested an exemption from 10 CFR Part 50, Appendix J. Paragraph III.A.3, which requires that all CILRTs be performed in accordance with ANSI N45.4-1972, " Leakage Rate Testing of Containment Structures for Nuclear Reactors." ANSI N45.4-1972 requires that leakage calculations be performed using either the Total Time method or the Point-to-Point method. The licensee has stated in support of the application
- for exemption from Appendix J that the Mass Point method is a more accurate method of calculating containment leakage. l l
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7590-01 i i
I It has been recognized by the professional communit) :: hat the Mau Point method is superior to the two other methods, Point-to-Point and Total Time, which are referenced in ANSI N45.4-1972 and endorsed by the present
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regulations. The Mass Point method calculates the air nass at each point in l time, and plots it against time. A linear repression lin, is plotted through the mass-time points using a least square fit. The slope-of this line is the leakage rate.
Draf t Regulatory Guide MS 021-5, which was published for comment in 1 October 1986, endorses, with exceptions, the ANSI /ANS 56.8-1981 standard and j
the Mass Point Method.
In addition to the method of calculation, consideration of the length of the test should also be included in the overall program. In accordance with 3
Section 7.6 of ANSI N45.4-1972, a test duration less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is only allowed if approved by the NRC staff, and the only currently approved ,
i methodology for such a test is contained in Bechtel Topical Report BN-TOP-), j Revision 1, " Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants," dated November 1, 1972. l This approach only allows use of the Tntal Time method. Therefore, tre staff will condition the exemption to require a minimum test duration of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the Mass Point method is used.
The licensee's letter also submitted information to identify the special circumstances for granting this exemptinn for the Haddam Neck Plant pursuant to 10 CFR 50.12. The purpose of Appendix J to 10 CFR Part 50 is to assure that containment leak-tight integrity can be verified periodically throughout the service lifetime so es to maintain containment leakage within the limit
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7590-01' l specified in the plant. technical specifications. The underlying purpose of
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the rule specifying particular methods for calculating ' leakage rates is to assure- that accurate and conservative methods are used to assess the results of containment leak rate tests. As set forth above, the Mass Point method has been a widely used method providing accurate results and the staff has determined that this method of calculating leakage satisfies the purpose' of the rule. i Based on the above discussion, the licensee's proposed exemption from paragraph III.A.3 of Appendix J, to allow we of the Mass Point method as !
i requested in the submittal dated July 10, 1987, is acceptable with the condition of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> minimum test duration, until such provision of Appendix'J is modified. Thereafter, the licensee shall comply with the provisions of such rule (or may renew its request for exemption). The exemption applies. i only to the. method of calculating leakage by use of the Mass Point method and ,
not to any other aspects of the tests.
i IV.
4 Accordingly, the Commission has determined that, pursuant to 10 CFR Part l i
50.12, this exemption is authorized by law, will not present an undue risk to the public health and safety, and is consistent with the common defense and security. The Commission has further determined that special circumstances, as set forth in 10 CFR 50.12(1)(2)(11), are present justifying the exemption, namely that application of the regulation in the particular circumstances is not necessary to achieve the underlying purpose of the rule. Accordingly, the Commission hereby grants an exemption as described in Section III above from l
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.l paragraph III.A.3 of Appendix J to the extent that the Mass Point method may be used for containment leakage ~ rate calculations, provided it is used with a minimum test duration of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The exemption is granted until such
-provision'of Appendix J is modified.. Thereafter, the licensee shall comply with.the provisions of such rule. The exemption-applies only to the method of i calculating leakage by use of the Mass Point method and not any other aspects 'I 1
of the tests. 'l Pursuant to 10 CFR 51.32, the Commission has determined that-the granting-of this' exemption will have no significant impact on the environment (52 FR 38026 , October 13,1987).
This exemption is effective upon issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 3
l nn . 6h . 1 e or .i Division of Reactor Proj 'ts III, IV, V l and Special Projects l Dated at Bethesda, Maryland this l15th day of October,1987 l
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