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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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7590-01 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION 1
l-l In the Matter of )
L )
L CONNECTICUT YANKEE ATOMIC POWER COMPANY ) Docket No. 50-213
)
.Haddam Neck Plant )
EXEMPTION 1.
The Connecticut Yankee Atomic Power Company (CYAPCO, the Licensee) is the holder of Operating License No. DPR-61 which authorizes operation of the
'Haddam Neck Plant. The license provides, among other things, that the Haddam -
Neck Plant is subiect to all rules, regulations, and Orders of the Comission now or hereafter in effect.
The plant is a single-unit pressurized water reactor at the licensee's site located in Middlesex County, Connecticut.
II.
One of the conditions of all operating licenses for water-cooled power reactors, as specified in 10 CFR 50.54(o), is that primary reactor containments shall meet the containment leakage test requirements set forth in 10 CFR Part 50, Appendix J. More specifically the following sections require that:
a Section III.A.6.(b), " Additional Requirements - Type A Test" "If two consecutive periodic Type A tests fail to meet the applicable acceptance criteria in III. A.S.(b), notwithstanding the periodic retest schedule of III.D. a Type A test shall be performed at each plant shutdown for refueling or approximately every 18 months, whichever occurs first, ggBQ$kh P
2
. until two consecutive Type A tests meet the acceptance criteria in III. A.5.(b),
after which time the retest schedule specified in III.D. may be resumed."
Section III.D.2.(a), " Type B Test"
" Type B tests, except tests for air locks, shall be performed during reactor shutdown for refueling or other convenient intervals but in no case at intervals greater than 2 years."
Section III.D.3, " Type C Test"
" Type C tests shall be performed during each reactor shutdown for refueling but in no case at intervals greater than 2 years."
By letter dated April 26, 1989, CYAPC0 requested a schedular exemption from the above requirements. Haddam Neck was last shutdown for refueling in July 1987 and the leak rate tests were performed over a period of the next 3 months. Haddam Neck was restarted in March 1988, after a 9 month outage and has operated essentially continuously since then, a total of 15 months. By September 5,1989 Haddam Neck will have operated 18 months and will be ready for refueling. However, the 18 month Type A test and the two year Type B and C test periods end before the next refueling on various dates beginning April 27, 1989.
III.
By letter dated April 26,1989 CYAPC0 requested a scheduler exemption from the regulatory requirements cited in Section II above. In this Section, the staff has evaluated the Type A and Type B and C test separately. The accepta-bility of the exemption requests for each item is addressed below. More details are contained in the NRC staff's related Safety Evaluation issued concurrent with this exemption.
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The Safety Evaluation and the above referenced submittal by the licensee are aveilable fcr public inspcction at the Comission's Public Document Room the Gelrt.an Building, 2120 L Street, N.W., kashington, D.C. 20555, and at the Russell Library,123 Broad Street, Middictown, Connecticut 06457.
SectionIII.A.6.(b)
As indicated above the intent of Appendix J was that after two consecutive f ailures of the integrated leat rate test (ILP.T) the plant should perform the ILET during eact refuelir5 cutage nct to exceed 18 ruenths. Hadcam Feck is prtsently schtduled tc cos. duct a refueling outage on or beforc September 5, 1989. Thc cremption would allow the ILRT to be pcstponed urtil that refueling cotage. Such an extensier cf approxir3ately 6 months is desirable in order tc 1
l prevent a mic' cycle shutdown. The *as found" failure of the ILRT has been due to 1
c> cessive Tyrt C lea kagts. CYAPCO bas taken aggressive actier.s to improve the Type C leatages. These efforts have included:
- 1) Impreving test precedures and methods,
?) l'aking modifications to penetration.s of poor performers,
- 3) Making modifications tc thc Service Water System to limit silt,
- 4) Conc'octing suppiecental Tyre C test, and
- 5) Tursuing an enhancec testing and maintenance program to identify, test, repair and reduce containment leakage.
Thc staff has reviewed these actions and agrees thest actions should reduce l
ientegt from historically peor penetrations and provide CYAPC0 a method to detect and focus its attentior. en future bad performers.
During the last refueling cutage unexpected core barrel and thermal shield repairt crtended ttc outage several months. During this time of approximately l 0 conths plant cuponents were not expcsed to the hermal operating temperature,
4 pressure and rediation conditions. The time interval of 18 months specified in
' Appencix J was based, in part, on the expected degradation of components exposed to the environment resulting from a full 18 months of normal plant-operations. The total exposure time for the containment to normal plant operation. environment at Haddam Neck Plant will be about 15 months.
Therefore the staff would not expect the containment condition to degrade significantly curing the extension of the test period.
Sectitn 111.D.2. (a) and III.D.3 As indicated above the intent of Appendix J was that isolation valves and the associated penetrations be tested durins, each refueling outage not to cxceed 24 mor.ths. Haddam I;eck is preser.tly scheduled to conduct a refueling outagc on or beforc September 5,1989. The exemption would allow the local leat rate tests (Type B and C) to be postponed until that refueling outage.
Such an extension of apprc>.imately 2 months is desirable in order to prevent a midcycle shutdown.
As noted in the 1. pe A test evaluation, CYAPCO has taken aggressive action
.to improve the chances of the of Type C leakage test of passing the ILRT.
Historically, Haddam tieck has not had a problem with Type B leakage. The t:RC staff has concluded that the actions taken by CYAPC0 should reduce leakage thrcugh historically poor penetrations and provide CYAPC0 a method to detect and focus attentien on future bad performers.
During the last refueling outage an unexpected core barrel and thermal shield repairs extended the outage several months. During this time of approximately 6 montns, plant components were not exposed to the normal cperating temperatures, pressure and radiation conditions. The time interval cf 24 months, specified in Appendix J, was based, in part, on the expected
(
[
4 degradation of cor:ponents exposed to the environment resulting from a full 2a months of normal plant operation. The total exposure time for the containment penetration to r.ormal plant operating environment will be only about 15 months.
The 24 month interval requirement for Type B and C penetrations is intended to be often enough to prevent significant deterioration from occurring and long encugh to permit the local leak rate tests (LLRTs) to be performed during plcnt outages. In addition leak testing of the penetrations during pknt- shutcown is preferable because of the lower radiation exposures to plant personnel. F.creover, some penetrations, beccuse of their intended functions, cannct be tested at power operation. For penetrations that cannot be tested during_ power operatier. or those that if testcd during plant operation would cause a ct. gradation in the plant's overall safety (e.g., the closiO5 of E recurdant lir.e in a safety system), the increase in confidence of containment integrity following e successful test is not significant enough tc justify a plant shutdowr specifically to perform the LLRTs within the 24 reonth time period, especially in light of the above discussions.
IV.
Pursuant to 10 CFR E0.12(a)(2)(v), the Commission will not consider granting a schedular exenption unless the licensee has made good f aith efforts to comp 13 with the regulation. The NRC staff believes that CYAPC0 has taken prudent steps to irnprove the containment integrity and if not for the extended refueling outage would have corrplied with Appendix J.
Eased on our evaluation, the NRC staff has concluded CYAPC0 has made good faitt cffort to comply with the requirements of Appendix J and that the special circurr. stances es described in 10 CFR 50.1?(a)(2)(v) exist and the scheduler exemptions ' rom 10 CFF, 50, Appendix J should be 5 ranted.
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b' V.
Accordingly, the Commission has determined that pursuant to 10 CFR 50.12, the exemption is authorized by law, will not endanger life or property or the ccmren defense and security, and is otherwise in the public interest. Therefore, the Commission hereby approves the following exemption request.
A temporary exemption is hereby granted from the requirement of 10 CFR 50, Appendix J, Section III.A.6.(b), which requires that an ILRT be conducted within 18 months of the last refueling outage for good cause shown, this exemption extenas that period by approximately 6 months from April 27, 1909.
A temporary exemption also is granted from the requirements of Sections III.D.2 (a) and III.D.3, which require a local leak rate test be conducted within 24 months of the previous refueling outage. For good cause shown, this exemption extends that period by approximately 2 months from July 18, 1989.
Pursuant to 10 CFR E1.32, the Commission has determined that the granting of this exempticn will have no significant impact on the environment (54 FR 27440).
This exemption is effective upon issuance.
FOR THE NUCLEAR REGULATORY C0tiMISSION w
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@ACL irectg ivision of Reactor Prd e ts 1/II Office of Nuclear Reacto egulation Dated at Rockville, Maryland this 14th day of August, 1989 l
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