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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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Text
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UNITED STATES OF AMERICA .
NUCLEAR REGULATORY COMMISSION In the matter of Docket No. 50-213 CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT f
EXEMPTION I.
The Connecticut Yankee Atomic Power Company (CYAPC0, the Licensee) is the hol. der 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 subject to all rules, regulations, and Orders of the Commission now or hereafter in effect.
The plant i.s a single-unit pressurized water reactor at the licensee's site located in Middlesex County, Connecticut.
II.
On November 19, 1980, the Comission published a revised Section 50.48 and a new Appendix R to 10 CFR Part 50 regarding fire protection features of l nuclear power plants. The revised Section 50.48 and Appendix R became j effective on February 17, 1981.Section III of Appendix R contains 15 sub-sections, lettered A through 0, each of which specified requirements for a particular aspect of the fire protection features at a nuclear power plant.
The licensee has submitted a request for exemption frcm the schedular requirementsof10CFR50.48(c)inaccordancewith'theprovisionsof ,
10 CFR 50.12(a)(2)(v) for a temporary exemption. Such a temporary exemption requires a demonstration by the licensee that it has made good faith efforts to comply with the applicable regulatory requirements. Further, Generic Letter 86-10 contains four criteria used by the staff to evaluate whether a licensee has demonstrated a good faith effort to meet the requirements under 10 CFR 50.48.
e60e270356 e60825 3 DR ADOCK 0500
i 1
These criteria are:
- 1) The utility has, since the promulgation of Appendix R in 1980, j proceeded expeditiously to meet the Connission's requirements.
{ 2) The delay was caused by circumstances beyond the utility's
. control.
! 3) The proposed schedule for completion represents a best effort l under the circumstances'.
- 4) Adequate interim compensatory measures will be taken until compliance is achieved. -
, III.
j Background l By a letter dated July 16, 1982 CYAPC0 requested an exemption from. .
f Section III.G.2.of Appendix R. 10 CFR Part 50 which proposed to relocate
} redundant shutdown systems within the switchgear room in lieu of providing alternate shutdown capability. CYAPC0 indicated at that time that the cost
- of an independent, alternate shutdown capability would be prohibitive. In ,
! a draft safety evaluation ' dated November 3,1982, the staff accepted CYAPC0 proposal for this area. The staff's final safety evaluation was issued by l letter dated November 14, 1984, in conjunction with the granting of eight exemptions from the requirements of Section III.G of Appendix R and approval of other plan +. modifications for the Haddam Neck plant to achieve compliance j with Appendix R. Tocomplywiththeschedularrequirementsof10CFR50.48(c),
i these modifications were to be completed before startup frorn the 1986 outage, which subsequently commenced on January 4,1986.
By letter dated March 7,1986, CYAPC0 requested a temporary exemption l from the schedular requirements of 10 CFR 50.48(c), which would defer implementation of the modifications to meet the requirements of Section
- 1 III.G of Appendix R for fire areas A-1, R-1, R-3, S-2, S-3, and T-1, in order to pursue a new approach for the switchgear room. Rather than relocating redundant electrical divisions for safe shutdown equipment witnin i
b l 1
1
the existing switchgear room and related plant areas, the licensee now proposes to construct a new building housing a switchgear room that would accommodate one shutdown division. The proposal associated with this exemption request is intended to resolve a number of other issues (tornado missiles, standby DC power, internal missiles and high energy pipe break effects), and, as such, represents a significant improvement in fire protection capability and overall plant safety as compared to the modifications referred to in the staff's November 1984 safety evaluation. The planning, construction and testing associated with this proposal would, subject to staff review, require schedular relief until start-up following the currently planned 1989 outage. This schedular extension would also apply to the specified fire areas which contain redundant shutdown-related cables that are impexted by the newly proposed switchgear room modifications.
l l Evaluation Criteria As stated in Section II above, the Commission provided criteria to be considered when granting schedular exemptions under 10 CFR 50.12(a)(2)(v).
The following is a discussion of how these four criteria have been satisfied.
- 1) The utility has, since the promulgation of Appendix R in 1980, proceeded expeditiously to meet the Commission's requirements.
Since the issuance of 10 CFR 50 Appendix R CYAPC0 has undertaken a number of fire protection reviews and evaluations, and has implemented many fire protection modifications. On March 19, 1981, CYAPC0 provided the NRC with the results of an initial comparison to Appendix R. The initial comparison to Appendix R and sut. sequent submittals resulted in numerous meetings with the Staff during the period of 1981 through 1984. Numerous Staff clarifications during this period r(quired additional submittals which culminated in a ,
favorable resolution of a related control room exemption request, ss described in the staff's November 1984 safety evaluation.
~
To date, CYAPC0 has performed fire protection modifications costing in excess of $3 million and the proposed switchgear room modifications will cost approximately an additional $10 million to complete. With the exception of 8 pending exemption requests, all other fire protection modifications have been completed.
Based on the above, the Commission concludes that the completed modifications reflect a reasonable effort to expeditiously comply with the requirements of 10 CFR 50 Appendix R.
- 2) The delay was caused by circumstances beyond the utility's control.
In a somewhat unique approach to the resolution of fire protection requirements, CYAPC0 prepared a risk-related document for specific plant fire areas. In March of 1982, the switchgear room, as preser.tly configured, was determined, based on the consultants' study, to be a negligible contributor to risk via internal fire events. Thus, rajor modifications to this fire area (S-2) were not proposed by the licensee. CYAPC0 later determined that the PRA consultant had made a major error in the switchgear assumptions which, when corrected, significantly impacted the calculated risk. ,
The resolution of the fire protection provisions for the control room, as described in the staff's November 1984 safety evaluation, included the need for a new remote instrumentation panel in the south end cf the switch-gear room. Related plant modifications further complicated tie modification design for the switchgear room and exacerbated the congestion in that area.
In June 1983, the staff isiued the Integrated Plant Safety Assessment Report for the Haddam Neck plant (NUREG-0826) which identified plant modifications and additional engineering studies resulting from the Commission's Systematic Evaluation Program (SEP). The licensee recognized that the contemplated modifications to the switchgear room could affect the i resolution of several SEP issues. The licensee subsequently determined that resolution of all of the issues related to the switchgear room would require that the modifications would have to be moved outside the switchgear room.
l
CYAPC0 eventually contracted the services of a consultant to develop a feasibility study of design alternatives to resolve all of the issues for the switchgear room. This study resulted in the proposal presented in the licensee's March 7, 1986 schedular exemption request. The current proposal
, represents a significant. improvement in both fire protection capability and overall plant safety as compared to the earlier modification design concept.
While it is not entirely clear to the staff why the proposed conceptual design for the switchgear room could not have been developed earlier, some of the delay resulted from circumstances beyond the licensee's control. The staff ,
agrees that the licensee was justified in awaiting resolution of all switchgear room issues before consnitting substantial resources to plant modifications which would also resolve the fire protection problem. While this judgment is a close one, the staff finds that this criterion is satisfied.
- 3) The proposed schedule for completion represents a best effort s
under the circumstante_s.
The licensee's March 7, 1986 letter presents a schedule for the proposed modifications including esi.imates for the lead time required for detailed design engineering, purchasing of all required equipment, and related construction activities. In view cf the magnitude of the proposed modifications and the lead time required to procure the necessary equipment, the staff agrees with the licensee's assessment that it would not be possible to perform all required modifications by the end of the next refueling outage. The staff concluded that, given that certain modifications can only be perfonned during refueling outages, the licensee's scheduled completion within two refueling outages represents a best effort possible under the circumstances.
l
- 4) Adequate interim compensatory measures will be taken until l compliance is achieved. '
The existing fire protection for the switchgear room and related areas consists of a smoke detection system, an automatic Halon fire extinguishing system or an automatic carbon dioxide suppression system, manual hose stations, and portable fire extinquishers. In addition, the licensee has proposed compensatory measures, in the form of a continuous fire patrol, (i.e., twenty-minute rounds) for the affected areas. The staff concludes that the continuous 1
~
fire patrol, in conjunction with the fire detection and suppression systems in the switchgear room and related plant areas provide reasonable assurance that any fire would be detected and extinquished before redundant divisions are affected by a fire in any one of the specified fire areas of sufficient size ,
to cause a loss of safe shutdown capability. On this basis, the staff further concludes that plant operation, in the interim, will not present an undue risk to the public health and safety.
IV.
Accordingly, the Commission has detennined that, pursuant to 10 CFR 50.12(a)(2)(v), the exemption would provide only temporary relief and the licensee has made a reasonable effort to ccmply with the schedular requirements of 10 CFR 50.48, in conjunction with the resolution of other important safety issues. The requested exemption is authorized by law and will no't endanger life or property or the comon defense and security.
Therefore, the Comission hereby grants a temporary exemption from the requirements of 50.48(c) and Section III.G of Appendix R to 10 CFR Part 50, with respect to' separation of electrical divisions in fire areas A-1A, A-1B, A-1C, A-10, R-1, R-3, S-2, S-3 and T-1 at the Haddam Neck plant until the end of the Cycle 15 refueling outage.
The granting of this exemption is subject to the licensee's submittal of major implementation milestones by September 30, 1986, and subsequent bimonthly progress reports. This exemption is also contingent on implementation of the comitments in the licensee's letter dated July 3,1986, which resulted from the fire protection inspection audit on June 16-20, 1986. These modifications will substantially improve the existing fire protection capability at the Haddam Neck plant in the interim. Failure to meet any milestone or implement any comitments will be considered a violation of the terms of the exemption and may result in the voiding of the exemption and subsequent. enforcement /
coniplianc.e action.
The Director, Office of Nuclear Reactor Regulation may grant changes to interim dates of the completion schedule if the licensee's request is timely I and shows good cause for the proposed change. However, the completion date for the fire protection modifications will remain the startup from the l cycle 15 outage. l
Pursuant to 10 CFR 51.32, the Comission has determined that the granting of this exemption will have no significant impact on the environment (51 FR 17696, May 14, 1986).
A copy of the Safety Evaluation dated August 25, 1986, related to this action .is e.vailable for public inspection at the Comission's Public Document Room, 1717 H Street, N.W., Washington, D.C. and at the local public document room located at the Russell Library,123 Broad Street, Middletown, Connecticut 06457. A copy may be obtained upon written request addressed to the U.S.
Nuclear Regulatory Comission, Washington, D.C. 20555. Attention: Director Divistoa of PWR Licensing-8.
T'iis Exemption is effective upon issuance.
Dated at Bethesda, Maryland this 25th day of August,1986 FOR THE NUCLEAR REGULATORY COMMISSION A
Harold R. Denton, Director Office of Nuclear Reactor Regulation 4
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