ML20204E988

Forwards Fr Notice Re Applications & Amends to OLs Involving NSHC

ML20204E988
Person / Time
Site:	Sequoyah
Issue date:	07/28/1986
From:	Office of Nuclear Reactor Regulation
To:	White S TENNESSEE VALLEY AUTHORITY
References
NUDOCS 8608010391
Download: ML20204E988 (15)

Text

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SUBJECT:

EJordan Sequoyah Nuclear Plant, Units 1 and 2 The following documents concerning our review of the subject facility are transmitted for your information. O Notice of Receipt of Application, dated . O Draf t/ Final Environmental Statment, dated . O Notice of Availability of Draft / Final Environmental Statement, dated . O Safety Evaluation Report, or Supplement No. , dated . O Notice of Hearing on Application for Construction Permit, dated . O Notice of Consideration of Issuance of Facility Operating License, dated . 50 Monthly Notice; Applications and Amendments to Operating Licenses involving no Significant Hazards Considerations, dated July 16, 1986 , (See page 25772) O Application and Safety Analysis Report, Volume . O Amendment No, to Application /SAR Jated . O Construction Permit No. CPPR- , Amendment No. _ dated . O Facility Operating License No. , Amendment No. , dated . O Order Extending Construction Completion Date, dated . O Other(Specify) Office of Nuclear Reactor Regulation

Enclosures:

As stated 860P010391 860728 cc. See next page PDR ADOCK 05000327 ! P PDR orric > PWR#4/0PWR!A PWR#4/DPWRfA '

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T *...* 28 JUL M DOCKET NO(S). : 50-327/328 Mr. S. A. White Manager of Nuclear Power Tennessee Valley Authority 6N 38A Lookout Place i 1101 Market Street l Chattanooga, Tennessee 37402:2801

SUBJECT:

Sequoyah Nuclear Plant, Units 1 and 2 l l The following documents concerning our review of the subject facility are transmitted for your information. I O Notice of Receipt of Application, dated O Draft / Final Environmental Statment, dated . O Notice of Availability of Draft / Final Environmental Statement, dated . O Safety Evaluation Report, or Supplement No. , dated O Notice of Hearing on Application for Construction Permit, dated l O Notice of Consideration of Issuance of Facility Operating License, dated 50 Monthly Notice; Applications and Amendments to Operating Li l Considerations, dated July 16, 1986 (See page 25Nes) involving no Significant Hazards l l C Application and Safety Analysis Report, Volume . l O Amendment No. to Application /SAR dated i i l O Construction Permit No. CPPR- , Amendment No. dated O Facility Operating License No. , Amendment No. , dated . O Order Extending Construction Completion Date, dated O Other(Specify) 1 Office of Nuclear Reactor Regulation

Enclosures:

As stated cc: See next page l l

i Mr. S. A. White

 !                     Tennessee Valley Authority             Sequoyah Nuclear Plant cc:

Herbert S. Sanger, Jr. , Esq. Tennessee Department of Public General Counsel Health Tenressee Valley Authority ATTN: Director, Bureau of 400 West Summit Hill Drive, E 11B 33 Environmental Health Services Knoxville, Tennessee 37902 Cordell Hull Building Nashville, Tennessee 37219 Mr. K. W. Whitt Mr. Michael H. Mobley, Director Tennessee Valley Authority Division of Radiological Health 400 West Summit Hill Drive, E3A8 T.E.R.R.A. Building Knoxville, Tennessee 37902 150 9th Avenue North Nashville, Tennessee 37203 Mr. Bob Faas Westinghouse Electric Corp. County Judge P.O. Box 355 Hamilton County Courthouse Pittsburgh, Pennsylvania 15230 Chattanooga, Tennessee 37402 Mr. Jerry Wills Tennessee Valley Authority SN 133B Lookout Place Chattanooga, Tennessee 37402-2801 Mr. Donald L. Williams, Jr. Tennessee Valley Authority 400 West Summit Hill Drive, W10B85 Knoxville, Tennessee 37902 Resident Inspector /Sequoyah NPS c/o U.S. Nuclear Regulatory Commission 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 Regional Administrator, Region II U.S. Nuclear Regulatory Commission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323

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g 4 25766 Federal Register / Vol. 51. No.136 / Wednesday, July 16, 1986 / Notices Bi Weekly Noece: Applications and Amendments to Operating ucenses involving No Significant Hazards Considerations

Background

Pursuant to Public Law (Pub. L) 97-415, the Nuclear Regulatory Commission (the Commission)is publishing this regular bl. weekly notice. Pub. L 97-415 revised sectionlasof the AtomicEnergy Act of 1954, as amended (the Act), to require the Commission to publish notice of any amendments issued, or proposed to be issued, under a new provision of section 189 of the Act.This provision grants the Commission the authority to issue and make immediately effective any amendment to an operating license upon a determination , by the Commission that such amendment involves no significant hazards consideration, notwithstanding the pendency before the Commission of a request for a hearing from any person. This bl. weekly notice includes all imendments issued, or proposed to be issued, since the date of publication of the last bi-weekly notice which was published on July 2,1986 (51 FR 24248), through July 7,1986. NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACIUTY OPERATING UCENSE AND PROPOSED NO SICNIFICANT HAZARDS CONSIDERATION DETERMINATION AND OPPORTUNITY FOR IIEARING The Commission has made a proposed determination that the following l amendment requests involve no l significant hazards consideration. Under I the Commission's regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendments would not (1) involve a significant increase in the probe bility or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.The basis for this

Federal Register / Vol. 51, No.136 / Wednesday, July 16. 1986 / Notices 25767 proposed determination for each Board up to fif'een (15) days prior to the the need to take this action will occur dmendment request is shown below. first prehearing conference scheduled in very infrequently. The Commission is seeking pubhc the proceeding. but such an amended A request for a hearing or a petition comments on this proposed petition must satisfy the specificity for leave to intervene must be filed with determination. Any comments received requirements descnbed above. the Secretary of the Commission. U.S. within 30 days after the date of Not later than fifteen (15) days prior to Nuclear Regulatory Commission, publication of this notice will be the first preheanng conference Washington, DC 20555, Attention: considered in making any final scheduled in the proceeding, a petitioner Docketing and Service Branch. or may determination. The Commission will not shall file a supplement to the petition to be delivered to the Commission's Public normally make a final determination intervene which must include a list of Document Room,1717 H Street NW., unless it receives a request for a the contentions which are sought to be Washington, DC, by the above date. hearing. litigated in the matter, and the bases for Where petitions are filed during the last Comments should be addressed to the each contention set forth with ten (10) days of the notice period. it is Rules and Procedures Branch, Division reasonable specificity. Contentions shall requested that the petitioner promptly so of Rules and Records Office of be limited to matters within the scope of inform the Commission by a toll. free Administration, U.S. Nuclear Regulatory the amendment under consideration. A telephone call to Western Union at (800) Commission. Washington. DC 20555. petitioner who fails to file such a 325-6000 (in Missouri (800) 342-6700). By August 15,1980, the licensee may supplement which satisfies these The Western Union operator should be file a request for a hearing with respect requirements with respect to at least one given Datagram identification Number to issuance of the amendment to the contention will not be permitted to 3737 and the following message subject facility operating license and participate as a party. addressed to fBronch Chief): petitioner's any person whose interest may be Those permitted to intervene become name and telephone number; date affected by this proceeding and who parties to the proceeding, subject to any petition was mailed: plant name: and wishes to participate as a party m the limitations in the order granting leave to

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publication date and page number of proceeding must file a written petition ntervene, and have the opportunity to this Federal Register notice. A copy of for leave to intervene. Requests for a participate fully in the conduct of the the petition should also be sent to the hearing, including the opportunity to Executive Legal Director, U.S. Nuclear ntervene eq e s or heanng and present evidence and cross-examine Regulatory Commission. Washington, petitions for leave to intervene shall be witnesses. DC 20555, and to the attorney for the filed in accordance with the If a hearing is requested, the licensee. Commission's " Rules of Practice for Domestic Licensing Proceedings" in 10 Commission will make a final Nontimely filings of petitions for leave determination on the issue of no to intervene, amended petitions, CFR Part 2. If a request for a hearing or significant hazards consideration. The supplemental petitions and/or requests petition for leave to intervene is filed by the above date, the Commission or an final determination will serve to decide for hearing will not be entertamed Atomic Safety and Licensing Board, when the hearing is held. absent a determination by the designated by the Commission or by the If the final determination is that the Commission, the presiding officer or the Chairman of the Atomic Safety and amendment request involves no presiding Atomic Safety and Licensing Licensing Board Panel, will rule on the significant hazards consideration, the Board, that the petition and/or request request and/or petition and the Commission may issue the amendment should be granted based upon a Secretary or the designated Atomic and make it immediately effective, balancing of factors specified ir.10 CFR Safety and Licensing Board will issue a n twithstanding the request for a 2.714(a)(1)(i)-{v) and 2.714(d). notice of hearing or an appropriate hearing. Any hearing held would take For further details with respect to this order, place afterissuance of the amendment. action, see the application for As required by 10 CFR 2.714, a If the determination is that the amendment which is available for public petition for leave to intervene shall set amendment involves a significant inspection at the Commission's Public forth with particularity the interest of hazards consideration, any hearing held Document Room.1717 H Street NW., the petitioner in the proceeding, and would take place before the issuance of Washington, DC, and at the local public how that interest may be affected by the any amendment. document room for the particular facility results of the proceeding.The petition Normally, the Commission will not involved. should specifically explain the reasons issue the amendment until the Boston Edison Company, Docket No. 30-why intervention should be permitted expiration of the 30-day notice period. 293, Pilgrim Nuclear Power Station, with particular reference to the However, should circumstances change Plymouth, Massachusetts following factors:(1) The nature of the during the notice penod such that failure petitioner's right under the Act to be to act in a timely way would result, for Date of amendment request: May 23. made a party to the proceeding;(2) the example,in derating or shutdown of the 1986. nature and extent of the petitioner's facility, the Commission may issue the Description of amendment request property, financial. or other interest in license amendment before the The proposed amendment would delete the proceeding: and (3) the possible expiration of the 30-day notice period, from the Technical Specifications the effect of any order which may be provided that its final determination is requirements to perform monthly visual entered in the proceeding on the that the amendment involves no inspections of the high energy piping petitioner's interest. The petition should significant hazards consideration.The outside of the primary containment also identify the specific aspect (s) of the final determination will consider all while the station is operating. subject matter of the proceeding as to public and State comments received Basis forproposed no significant which petitioner wishes to intervene. before action is taken. Should the hazards consideration determination: Any person who has filed a petition for Commission take this action, it will The Commission has provided leave to intervene or who has been publish a notice of issuance and provide standards in 10 CFR 50.92(c) for admitted as a party may amend the for opportunity for a hearing after determining whether proposed license petition without requesting leave of the issuance. The Commission expects that amendments involve significant hazards

a 25768 Federal Register / Vol. 51, No.136 / Wednesday, July 16, 1986 / Notices , considerations. These standards have event of a high energy line break outside included in the technical specifications. been addressed by the licensee as primary containment. Since for example, a more stringent follows: compensatory measures in the form of surveillance requirement, would not P' * ** 5"*P *" ' " ** ** to CFR 50.92(c/(11 states that the necessary until those permanent The stafff has reviewed the proposed pmposed arnendment should not.. .. modifications could be made, and they license amendments and concluded that

                     '                    have    been  completed. the proposed         they fall within the envelope of example e   a$il$ty or nseqven s a amendment does not m, volve a                 (ii) since the use of a qualified accidentpreviously evaluated. . ."         significant reduction in a margin of          mdependent auditor to augment the The present requirement was imposed safety.                                           current licnesees' audit process by the NRC through Amendment No. 7            Based on the above analysis, the           constitutes a more stingent surveillance to Facility Operating License No. DPR-     licensee concluded that its amendment         requirement than performing audits only

35. An NRC safety evaluation titled request involves no significant hazards using licensee personnel. I

" Analysis of the Consequences of High consideration.The staff has reviewed Accordingly, the staff proposes to Energy Piping Failures Outside the licensee's no significant hazards determine that the proposed license Containment, dated December 20,1974, determination and agrees with the amendments do not involve a significant was written in support of Amendment licensee's analysis. Therefore, the staff hazards consideration. No. 7. This safety evaluation contains proposes to determine that the LocalPublic Document Room the results of Boston Edison Company requested amendment involves no locations: Russell Library,123 Broad (CECO) and NRC reviews of the , significant hazards considerations. Street, Middletown, Connecticut 06457, consequences of high energy pipmg Local Public Document Room and Waterford Public 1.ibrary,49 Rope failures outside primary containment. location: Plymouth Public Library,11 Ferry Road, Waterford, Connecticut The safety evaluation also established North Street. Plymouth, Massachusetts 06385 the critena to be applied should BECo 02360. request permanent relief from the-Attorneyfor licensee: Gerald Garfield, Attorneyforlicensee: W.S. Stowe, Esquire, Day, Berry and Howard, reqmrement to perform these monthly Esq., Boston Edison Company,800 visual inspections. These criteria Counselors at Law, City Place, Hartford, Boylston Street. 36th Floor. Boston, specified that certain modifications must Massachusetts 02199. Connecticut 06103-3499. be completed at Pilgrim Station before NRC Project Director:JohnA. the operating restriction would be Zwolinski. Grime , so d 1. d Vin e t mod ic tio s discuss in the safety C y Co sob ed Edison Company of New evaluation have been completed and are C Yodc Docket No.50-247. Indian Point mcorporated into design documents. The Neck Plant. Middlesu County Nuclear Generating Unit No.2 Connecticut: Northeast Nuclea Energy nt nstaH Company, Docket Nos. 50-245,50-336 Westchester County, New York kup RI va es or e and SN23, Millstone Nuclear Units Date ofAmendment request:May 9, equipment area cooling units located . within the RCIC pump compartment. A Nos.1,2, and 3 New London County. 1986. Connecticut. documented reevaluation concluded Discription of amendment request: that this modification is not necessary Date of amendment requests:May 30. The proposed amendment would revise because an adequate floor separates the 1986. the Technical Specifications to correct cooling lines from any potentially Description of amendment requests: typographical errors contained in generated missiles.Therefore there Cenetic Letter 82-21 specifically states Consolidated Edison's amendment should not be a significant increase in that an individual / group not associated application dated April 10,1986 and the the probability or consequences of any with the utility should perform the fire subsequently issued Amendment No. of the previously evaluated accidents. protection audit at least once every 3 110 issued March 3,1986, the Facility years. The proposed license Operating License No. DpR-26. 10 CFR 50.92/c//2/ states that the amendments would revise each plant's Specifically the proposed corrections proposedamendmentshouldnot". . , technical specifications to include the are in section 3.10.2.1(b) and include Create the possibility of a new or use of a qualified outside fire protection insertion of a less than or equal sign different kind of accident from any consultant independent of Northeast preceeding 25% steam generator tube accident previously evaluated. ." Utilities at least every 3 years, plugging and the deletion of the The imposed operating restriction was Basis forpmposedno significant denominator P following the factor 4.64 considered to be a temporary measure hazards considemtior detennination: in the hot channel factor equation for P until the modifications reviewed in the The proposed license amendments less than or equal to 0.5. NRC safety evaluation are completed. provide an improved level of fire Basis forproposedno significant BECo has completed the necessary protection in that the triennial fire hazards consideration determination: modifications: therefore, the possibility protection and loss prevention audits The Commission has provided guidance of a new or different kind of accident will be performed by a qualified fire concerning the applicatio. of the will not be created by delection of the protect on consultant, which will standards in to CFR 50.92 by providing compensatory inspection requirement. augment the audit process currently certain examples (48 FR 14870). One of performed by utility personnel. The the examples (i) of actions not likely to 10 CFR 50.92/2//J/ states that the Comrmssion has provided examples (48 involve significant hazards F.mpos mendme s ould FR 14870. Apnl 6.1983) of actions not f y ,#8 ,eb in considerations relates to a purely likely to involve significant hazards admimstrative change to technical a margin of safety, considerations. Example (ii) of this specifications: for example a change to The completed modifications guidance states that a change that achieve consistency throughout the descnbed in FSAR Supplement No. 34 constitutes an additional limitation, technical specifications. correction of an increases the margins of safety in the restnction or control not presently error or a chenge in nomenclature. The

Federal Register / Vol. 51. No.138 / Wednesday, July 16. 1986 / Notices 25769 proposed revision to the Technical planar exposure to Figures 3.10-4 and bundle operating power. Keeping the Specifications is consistent with 3.10-5 for the GE type P8DRB299 fuel, bundle power below the critical power example (i) in that the proposed change The changes to allow for greater will keep (1) the fuel rod heat transfer in corrects an error. Therefore, the staff flexibility during startup and power the nucleate boiling regime which is a proposes to determine that the escalations are to increase (1) the APRM higher heat transfer process than the amendment does not involve a flux scram setting and (2) the rod block transition boiling regime and (2) the significant hazards determination. setting. And the change to account for cladding temperture at a lower value for Loco / Public Doca ment Room the arrangement of the new and old fuel the heat transfer rate. The MCPR is locotion: White Plains Public Library, types in the core is to increase the greater than 1.0 to account for errors in 100 Martine Avenue. White Plains. New MCPR limit. calculations and instrumention. De York.10610. The Cycle to core for Oyster Creek MCPR would be increased by the Attorneyforlicensee: Brent L consisted of Exxon Type VB assemblies. proposed amendment which is changing Brandenburg. Esq 4 Irving Place. New GE Type P8DRB239 assemblies and GE the MCPR in the conservative direction. York. New York 10003. Type P8DRB285H assemblies. He Cycle Amendment No. 75. Cycle 10 NRCProjectDirector: Steven A. 11 core will consist of Exxon Type VB Refueling, dated August 24,1984. Varga. assemblies. GE Type P8DRB239 authorized changes to the TS to allow GPU Nuclear Corporation. Docket No. assembnes. GE Type P8DRB285H operation of Oyster Creek with the 50-219. Oyster Creek Nuclear assemblies. GE Type P8DRB299ZA Cycle 10 reload. The NRC's safety assemblies and GE Type P8DRB299Z evaluation for Amendment No. 75 was Generating Station. Ocean County, New p,,,Y assemblies.The GE Type P8DRB299ZA based on the NRC staff's comparison of assemblies and GE Type P8DRB299Z NEDO-24195. " General Electric Reload Date of omendment mquest: June 17 assemblies are both included in the Fuel Application for Oyster Creek." with 1986 (TSCR 149). requirement being proposed for the GE NEDO-24011. " General Electric Boiling Desenption ofomendment mquest: Type P8DRB299 fuel The proposed amendment would make Water Reactor Generic Reload Fuel The MAPUiGR is the maximum in- Application." NEDO-24011 has been changes to section 2.3. Limiting Safety core value of the average of the linear System Settings, and to section 3.10. reviewed and approved by the staff for heat generation rate for all the fuel reference in the safety analysis of Core Limits,of the Appendix A bundles at any given horizontal plane Technical Specifications (TS) to account across the core. The linear heat boiling water reactors. The staff for the Operating Cycle 11 reload. The concluded that the procedures employed generation rate is the rate of generating in the Cycle 10 reload design and changes to section 2.3 would increase (1) heat from a fuel bundle per unit length the neutron flux scram setting for the analYsis for Oyster Creek were of the bundle in kilowatts per foot.TS cverage power range monitors (APRM) and (2) the neutron flux, control rod 3.10.A2. requres during power operation that the average linear heat generation h"d",'),o*,g'y'*p'py '[ ' g block setting. The changes to section report and were acceptable. In addition. rate of all the rods in any fuel bundle at the staff concluded that the procedures 3.10 would increase the minimum any axiallocation shall not exceed the critical power ratio (MCPR) limits and used by the licensee to establish MAPUlGR limits in Figure 3.10-4 (for 5 revise the maximum allowable average perating limits were acceptable. The loop operation) and Figure 3.10-5 (for 4 planar linear heat generation rate safety analyses performed by the loop operation). This requirement limits (MAPUlGR) for five loop and four loop the maximum heat generation rate int he licensee in support of the Cycle 11 operation in Figures 3.10-4 and 5. rei ad core design use the methods core during power operation to prevent respectively. The changes to the figures the fuel rod peak cladding temperature described by NEDO-24195. The are to replace the MAPUIGR for the from exceeding a maximum acceptable Appendix D to NEDO-24195. which is a existing fuel type P8DRB265L by that for value in any accident This acts to summary of results of the Cycle 11 , the new feel type P8DRB299. The prevent fuel damage in the accident. rel ad core design and safety analysis, l MAPUiGR for the existing fuel types The APRM uses local neutron flux to is attached to the licensee's June 17 P8DRB239 and P9DRB265H in Figures calculate the average neutron flux or 1988. application to support the 3.10-4 and 3.10-5 are not being changed power of the reactor core.The APRM licensee's proposed changes to the TS. by this proposed amendment. Included system receives the reactor circulation The licensee stated that, with respect with these proposed changes are flow rate to establish the flow bias trip to the MCPR limit calculated by (GE), proposed changes to the Basts for TS signal which is being changed by this the Rod Withdrawal Error transient sections 2.3 and 3.10. proposed amendment.The APRM flow (RWE) was the most limiting for Cycle Basis forproposedno significant bias tdp settingis to scram the reactor 11 with a maximum Delta CPR of 0.38. hazards consideration determination core on too high a core power for the This represents an increase from the The licensee has proposed Technical reactor flow rate. The rod block monitor Cycle 10 value which was 0.33. The Specification Change Request (TSCR) determines the local core power in the licensee explained that the main reason No.149 to (1) take into account the use vicinity of a control rod selected for for the increase is that the RWE was of new General Electric (GE) Type movement and blocks the rod movement performed with the proposed Rod Block P8DRD299 fuel assemblies in the core in if the local power is excessive for the maximum setpoint at 108% for Cycle 11 operating Cycle 11. (2) allow greater reactor flow rate.The flow bias setting while the original analysis for Cycle 10 flexibility during startup and during for blocking rod movement is also being used the current Rod Black maximum power escalations to plant rated. power changed by this proposed amendment. setpoint of 106%. The licensee stated operating conditions, and (3) take into The MCPR is the smallest critical that the proposed MCPR value of 1.45 I account in op erating Cycle 11 the power ratio (CPR) allowed in the core was conservatively chosen but that this ( arrangement of the new fuel type and during power operation. The CPR is the should not create operating difficulties the existing fuel type from operating ratio of the critical power for the fuel because the licensee expects the plant Cycle 10. The changes to account for the bundle, where the nucles;e boiling to operate with an MCPR margin of at new fuel type are the changes to add the process breaks down within the bundle least 20% in operating Cycle 11. The MAPLIIGR as a function of the average and transition boiling commences. to the licensee explained that the APRM scram i I

25770 Federal Register / Vol. 51, No.136 / Wednesday. July 16, 1986 / Notices' , and rod block settings were modified to Indiana and hiichigan Electric Company, (51 FR 20902); corrected June 16,1986 (51 allow greater flexibility during startup Docket Nos. 50-315 and 50-316, Donald FR 21813). and power escalation to related C. Cook Nuclear Plant, Unit Nos.1 and Evpiration date ofindividualnotice: conditions. 2. Berrien County Michigan July 8,1986. With respect to the MAPLHCR limits. Date of amendment request: May 30, LocalPublic Document Room the licensee stated that the emergency. 1986 supplemented on June 23,1986. location: State University of New York. core cooling system responses and heat Description of amendment request: Penfield Library, Reference and transfer coefficients remained The proposed amendment would revise Documents Department. Oswego, New unchanged from the previous reload the Technical Specifications by adding York 13128. evtluitions. The only differences requirements on the fire-unaffected Unit Northern States Power Company, b; tween this proposal and the previous to support the alternate safe shutdown Docket Nos. 50-282 and 50-306 Prairie Cycis 10 analysis are in the Cycle 11 fuel or emergency remote shutdown of the Island Nuclear Generating Plant, Unit bundle nuclear characteristics because opposite fire-affected Unit. The changes Nos.1 and 2. Goodhue County of the new GE fuel type.The licensee are necessary to meet the requirements Minnesota stated that operatmg the Cycle 11 fuel of to CFR 50. Appendix R. Basis forproposedno significant Date of amendments request: lune 6. bundles withm the proposed MAPHGR N limits will ensure that the peak clading hazards considerauon determinadon: The Commission has provided guidance Description of amendments request temp;ratures will not exceed 2200- The proposed amendmen's would during a Ioss-coolant accident. concerning the application of the standards for making a no significant incorporate operability and testing B: sed on the above the staff has hazards determination by providing requirements related to the inadequate concluded tho' operation of the Oyster certain examples (51 FR 7744). One of core cooling instrumentation systems Crnk plant in occordance with the these examples (ii)is a change that (ICCI) associated with the subcooling proposed amendment: constitutes an additional limitation, margin monitors, core exit restriction, or control not presently thermocouples and the reactor vessel (1) Does not mvolve a significant level instrumentation systems (RVLIS) increase in the probabilitIor included in the technical specifications. The change to add requirements for the at the Prairie Island Nuclear Generating [# ',9",#{Ce8 f[' previously evaluated alternate or remote shutdown capability Plarit Unit Nos.1 and 2. The licensee

          ,                                                                                 was requested by our Generic Letters from the fire. unaffected Unit to the fire, The proposed amendment would keep affected Unit is directly related to this            82-28 and 83-37 to install ICCI systems tha core fuel operating conditions in      example.Therefore, the Commission              and propose technical specifications to opir: ting Cycle 11 within safe operating proposes to find that the changes do not         assure adequate operability and testing of these instrumentation systems.

limitations based on analyses previously involve a significant hazards approved by the staff. consideration. This proposed technical specification LocalPublic Document Room is in response to Generic Letters 82-28 (3) Does not create the possibility of a location: hiaude Preston Palenske and 83-37 and in accordance with the new or different kind of accident from Memorial Library,500 Market Street St. licensee's application for amendments any accident previously analyzed Joseph, Michigan 49085. dated June 6,1986. because: Attorneyforlicensee Gerald Before issuance of the proposed Charnoff, Esquire, Shaw, Pittman, Potts license amendments, the Commission The proposed amendment is based on will have made findings required by and Trowbridge,1800 M Street NW., anaIyses which have been previously Atomic Energy Act of 1954 as amended reviewed and approved by the staff. Washington, NRC ProjectDC 20036'r: Directo B.J. (the Act) and the Commission's (3)Does not involve a significant Youngblood. regulations. t reduction in a margin of safety because: Nlagara Mohawk Power Corporation, Basis forproposed no significant hazards consideration determination: , The proposed amendment would keep Docket No. 50-220, Nine Mile Point The Commissioa has made a proposed ( the Cycle 11 fuel operating conditions Nuclear Station, Unit No.1. Oswego determination that the request for within acceptable limits. County, New York amendment involves no significant l i Therefore, because the licensee's Date of amendment request: May 27, hazards consideration. Under the I request meets the above three criteria in 1988. Commission's regulations in 10 CFR 10 CFR 50.92(c), the staff proposes to Brief Description of amendment: The 50.92, thin means that operation of the d termine that the licensee's proposed proposed amendment would modify facility in accordance with the proposed change does not involve a significant Technical Specification section 6.12, amendments would not (1) involve haz:rds consideration. High Radiation Area. Table 3.6.2a. significant increase in the probability or Instrumentation That Initiates Scram, consequences of an accident previously LocalPublic Document Room evaluated:(2) create the possibility of a location: Ocean County Library,101 Table 3.0.2b Instrumentation that initiates Pnmary Coolant System or new or different kind of accident from W:shington Street. Toms River, New Containment Isolation. Table 3.6.2h, any previously evaluated; or (3) involve l i Jena 08753. Vacuum Pump Isolation, and the notes a significant reduction in a margin of Attorneyforlicensee Ernest L Dlake, to these tables to allow Niagara safety. Jr.: Shaw, Pittman, Potts, and Mohawk to demonstrate the feasibility The Commission has provided Trowbridge,1800 M Street NW., of a Hydrogen Water Chemistry System guidance concerning the application of Washington, DC 20030. as a mitigator ofintergranular stress standards for making a no significant VRC Project Director: John A. corrosion cracking of stainless steel hazards consideration determination by Zwolinski. piping at Nine Mde Point Unit 1. providing examples (48 FR IM70). One Date ofpublication ofindividual of the examples (ii) of actions not likely notice in Federn/ Register

• june 9.1986 to involve a significant hazarc5

Federal Register / Vol. 51, No.136 / Wednesday, July to.1986 / Notices 25771 consideration involves additional Response The proposed Technical Specifications provides for new limitations, restrictions, or controls not Specification changes reflect existing instrument setpoints which include pt:sently included in the technical plant instrumentation configuration. allowance for instrument errors. These specifications. Specifically, the proposed This configuration is described in the changes were previously submitted on technical specification change will Final Safety Analysis Report (FSAR). June 21.1985 and noticed in the Federal impose additional restrictions requiring Plant system operation or functions will Register on August 14,1985 (50 FR operability of the ICCI systems and not be affected and new systems or 32801). specifying testing of the ICCI systems. equipment are not being introduced. Basis forproposedno significant These additional restrictions have been Therefore, the Technical Specification hazards consideration determination: requested by GLs 82-28 and 83-37 and changes will not involve any significant The basis provided in the previous by our letter dated May 8,1986. On this increase in the probability or notice remains valid. brsis, the staff believes that this consequences of an accident previously LocalPublic Document Room amendment application is enveloped by evaluated, location: Greeley Public Library, City sxample (ii) and proposes that this (2) Does the proposed license Complex Building. Greeley, Colorado. chtnge does not involve a significant amendment create the possibility of a Attorneyforlicensee: Bryant hazards consideration. new or different kind of accident from o Donnell. Public Service Company of LocalPublic Document Room any accident previously evaluated? Colorado, P.O. Box 840. Denver, location: Environmental Conservation Response A new or different kind of Coloradt 80201. Library, Minneapolis Public Library,300 accident cannot be created by the NRC Project Director: Herbert N. Nicollet Mall, Minneapolis, Minnesota. pr posed changes. As discussed in Berkow. A ttorney for licensee: Gerald Charnoff NUREG/0611. analyses performed by Esq., Shaw, Pittman Potts, and Westinghouse have demonstrated that Southern California Edison Company, et Trowbridge.1800 M Street NW. the anticipatory reactor trip on turbine al Docket Nos. 50-361 and 50-362. San Washington, DC 20036 trip will reduce the ensuring Reactor Onofre Nuclear Generating Station. NRC Project Director. George E.1. ear. Coolant System pressure transients. Units 2 and 3, San Diego County, This proves to be beneficial to the safe Califorma P wer Authority of The State of New shutdown of the plant during certain York, Docket No. 50-286, Indian Point Date of Amendment Request: April 27 overpressure transients. The changes 1984 and August 29,1985 (Reference Unit No. 3. Westchester County, New incorporate an existing instrument trip York PCN-111) condition into the Technical Description of Amendment Request: Date of amendment request April 30. Specifications.The function of systems PCN-111 would revise Table 4.11-2, ggg, and equipment have not been impacted " Radioactive Caseous Waste Sampling Description of amendment request, by the changes. and Analysis Program" of Technical (3) Does the proposed amendment Ths purpose of this proposed change is Specification 3/4.11.2, " Gaseous to ir.clude an anticipatory reactor trip involve a significant reduction in a Effluents." and Technical Specification upon turbine trip in the Indian Point 3 margin of safety? 3.11.2.3, " Dose.Radioiodines. Technical Specifications. NUREG-0611. pro ose esadd an ankcipat 'Y n 9, pp , , ne Radioactive Materials in Particular Form

      " Generic Evaluation of Feedwater                                                               and Tritium. in order to allow disposal trip.The incorporation of an existing Transients and Small Break Loss-of-                                                             of radioactively contaminated reactor Coolant Accidents in Westinghouse-           instrumentation trip condition into the coolant pump (RCP) motor oil, turbine cano Designed Operating Plants." describes enalyses performed by Westinghouse

[IS[c g t at Generic Letter building sump and other waste oil by meineradon. 82-18, item II.K.3.12, will be satisfied. which demonstrates that the T.S. %.11.2 provides the maximum Therefore, these changes does not anticipatory reactor trip on turbine trip d se rates at which radioactive gaseous involve any significant reduction in a will reduce the ensuing Reactor Coolant effluents may be released into the System pressure transients.

                                                  "'                 g,,7 Th   s aff a e s with the licensee's     envir nment. Table 4.11-21ists the The anticipatory reactor trip on          assessment and proposes to determine               different types of radioactive gaseous turbine trip may be blocked during                                                              releases and specifies sampling and that the proposed changes do not                           ,

turbme overspeed surveillance testing in involve a significant hazards analysis requirements to verify that order to ensure safe operation of the consideration dose rates are within the limit. turbine overspeed trip. LocalPublic' Document Room Currently, Table 4.11-2 does not The licensee has previously confirmed location: White Plains Public Library, recognize incineration of waste oil as a that Indian Point 3 has an anticipatory 100 Martine Avenue, White Plains. New release type.The proposed change rMctor trip on turbine trip (IP-80-117)* York 10601. would revise Table 4.11-2 to reflect dated December 30,1980). 'Ihis change Attorneyfor //censee: Mr. Charles M. incineration of oil as a release type and merely adds additional surveillance to Pratt,10 Columbia Circle New York, specify sampling and analysis an existing condition. New York.10019. requirements which must be met prior to Basis forpivposedno significant NRC Project Director: Steven A. incineration in order to veriiy that the hazards consideration determination:In Varga. dose limit will not be exceeded. tccordance with the requirements of 10 T S. 3.11.2.3 specifies limits on dose CFR 50.92, the licensee has determined Public Service Company of Colorado, which an individual may receive due to this applicati6n to involve no significant Docket No. 56-287 Fort St. Vrain radiciodines, radioactive materials in hazards as stated below: Nuclear Generating Station Platteville, particulate form and tritium released (1) Does the proposed license Colorado from the plant in any calendar quarter amendment involve a significant Date of amendment request May 15, and calendar year. The proposed change increase in the probability or 1988. would revise T.S. 3.11.2.3 to limit the consequences of an accident previously Description of amendment request: dose contribution resulting from the evaluated? The proposed changes to the Technical incineration of oil to less than 0.1% of

25772 Federal Register / Vol. St. No.136 / Wednesday, July 16, 1986 / Notices the specified dose limits for radio- specification limit in Section 3/4.11.2.3.2 Tennessee Valley Authority, Docket iodines, particulates, and tritium. ana it considered to be an insignificant Nos. 50-327 and 50-328, Sequoyah Basis forProposedNoSignificant contribution to dese via this pathway. Nuclear Plant, Units 1 and 2, Hamilton Hazards Consideration Determination: The proposed technical specification County, Tennessee 10 CFR 50.92 states that a proposed would require calculations of doses amendment to an operating license Date of amendment request: April 10. associated with the incineration of each 1986. involves no significant hazards barrel, and would limit the accumulated consideration if operation of the facility dose during a calendar quarter or #8## #".## #I###" ### # in acc ance with proposed calendar year to less than 1% of 10 CFR p s 9 d , ge ' ac o an Sys e (1) Involve a signific'a nt increase in 50 Appendix Ilimitm, g does objectives. Pressure Isolation Valves" from the tha probability or consequences of an This is an appropriate small fraction of Technical Specifications. The valves accident previously evaluated; or such limits for this source and is listed in Table 3.4-1 prevent leakage (2) Create the possibility of a new or considered to be As Low As la from the reactor coolant system, which different kind of accident from any Reasonably Achievable. In addition to is a high. pressure system,into a lower accident previously evaluated; or the above considerations, the equipment pressure system. In order to ensuro (3) Involve a significant reduction in a used to incincerate waste oil will not be proper control of any eliminations or margin of safety, interconnected with or in the immediate additions to the table,it would be in accordance with 10 CFR 50.91(a)(1) vicinity of safety.related systems, and placed in the appropriate plant the licensee submitted the following thus will not have an impact on instructions; therefors, changes would analysis of the proposed amendment previously evaluated accidents. have lo be evaluated against the criteria using the criteria of 10 CFR 50.92. given in the Code of Federal

2. Willoperation of thefacilityin The proposed change discussed above Regulations Tit'e 10 Part 50.59(a)(2),(10 shall be deemed to constitute a accordance with thisproposed gg $n,59 2 ignificant hazards ccnsideration if amendment create the possibility of a .

there is a positive finding in any of the following areas. new or different kind of accident from any accident previously evaluated? osh,sfo pMpo

                                                                                                      , gg f nog,, sign. .icanj ,

The NRC published guidance in the L Willoperation of thefacilityin Response: No. Federal Register (51 FR 7744) concerning accordance with this pmposedchange Release of the radioactivity contained examples of amendments that are not in volve a significant increase in the in the oil meets the requirements of10 likely to involve a significant hazards probability or consequences of an CFR Part 20 and 10 CFR Part 50 consideration. accidentpreviously evaluated? Appendix 1, and thus does not constitute Example (i) provided in 51 FR 7744 Response: No. an accident. identifies a proposed amendment to an The release of the radioactive , operating license likely to involve no mIterial contained in the oil does not 3. Willoperation of thefacilityin significant hazard if it is "a purely constitute an accident evaluated in the accordence with this proposed administrative change to technical Final Safety Analysis Report. amendment involve a significant specifications." The TVA requested Compliance with 16 CFR Part 20 reductionin margin ofsafety? change would be purely administrative Appendix B. Table 11 Column I, and dose since it would alter the method of listing Response: No* objectives of 10 CFR Part 50, Appendix 1. the pressure isolation valves. There insures that the health and safety of the Release of the radioactive material would be no change to the plant design, public will not be endangered and that contamed in the oil will not result in a configuration, or testing requirements, there will be no significant impact by significant reduction in a margin of and any changes made to the table ths Station on the environment. safety because as, discussed above, the requirements of 10 CFR Part 20 and to would still require a 10 CFR 50.59(a)(2) - Concentrations of any radioactivity ,,yg,,, 1:aving the Station will be calculated CFR Part 50 Appendix I will be met Accordingly, the Commission and documented per methods in the The staff has reviewed the licensee.a proposes to determine that these Offsite Dose Calculation Manual.The analysis and concludes that the proposed amendments to the TS involve potential dose that could occur as a proposed amendment satisfies the' no significant hazards considerations, result of the incineration of criteria of to CFR 50.92. Based on that contaminated oil has been calculated. LocolPublic Document Room conclusion the staff proposes to Tha highest radioactivity concentration location: Chattanooga. Hamilton County would probably be less than 4.6 uCi per determine that the proposed amendment Bicentenial1.ibrary,1001 Broad Street, does not involve a significant hazards Chattanooga, Tennessee 37401. drum based on the results of the highest consideration-concentration in Reactor Coolant Pump Attorney for licensee: Mr. Herbert S. LocalPublic Docuent Room Sanger, Jr., Esquire, General Counsel, oil from an 860 MwE net unit owned by another utility (0.2 uCi Cs58,0.3 uCi Locatis General 1.ibrary, University of Tennessee Valley Authority,400 Co-co,1.0 uCi Cs-134, and 3.1 uCi Cs- California at Irvine, Irvine, C'difornia Commerce Avenue E11B33, Knoxville, 92713. Tennessee 3M2. 137 per drum). Assuming this w arst case , concentration were the average for all Attorneyfor Licensee: Charles R. NRCProject Director: B.l. 1000 gallons incinerated per year at San Kocher, Esq., Southe'n California Edison Youngblood. Onofre, the dose to any organ of the Company,2244 Walnut Grove Avenue, maximum exposed individual (a child at P.O. Box 800, Rosemead. California Virginia Electric and Power Company, the nearest residence located 1.3 miles 91770 and Orrick Herrington & Sutcliffe, Docket Nos. 50-280 and 50-281, Surry NNW of the plant) was calculated to be Attn.: David Pigott, Esq., COO Power Stabon, Unit Nos.1 and 2, Surry 0.001 mrem /yr based on a X/Q of1.2 E- Montgomery Street, San Francisco, County, Virginia 8 6 sec/m and a D/Q of 4.5 Fe9 m-8.This California 84111. Date of amendment mquests: June 16. dose is 0.01% of the technical NRC Director George W. Knighton. 1986.

Federal Register / Vol. 51, No.136 / Wednesday, July 16, 1986 / Notices 25773 Description of amendment requests: MRC Project Director: Lester S. Duke Power Company. Dockat Nos. 56-The proposed change would revise the Rubenstein. 369 and 50-370, McGuire Nuclear audit frequency of Surry Power Station's PREVIOUSLY PUBUSIIED NOTICES Station, Units 1 and 2, Mecklenburg Security Plan to occur at least once per County, North Carolina OF CONSIDERATION OF ISSUANCE 12 months instead of 24 months.This Date amendment request: May 15. OF AMENDMENTS TO OPERATING

                                          '         UCENSES AND PROPOSED NO                   1986, as supplemented May 23,1986.

he Techn c Spec fications onsfs"te SIGNIFICANT HAZARDS Brief description of amendment: The with the re9uirements of to CFR Part CONSIDERATION DETERMINATION amendment would revise the Technical 73.40(d)* AND OPPORTUNITY FOR HEARING Specifications to reflect the third of Basis forproposedno significant The following notices were previously several refueling stages involved in the hazards considemtion determmation: published as separate individual continuing transition to the use of Pursuant to 10 CFR 50.92. the notices.The notice content was the optimized fuel assembles in Unit 1. proposed change does not involve a same as above.They were published as Date ofpublication ofindividual significant hazards consideration individual notices because time did not notice in Fedem/ Register: June 27,1986 because operation of Surry Units 1 and 2 allow the Commission to wait for this bi. (51 FR 23484). in accordance with the change would weekly notice. They are repeated here Expiration date ofindividualnotice: not: because the bi weekly notice lists all July 28,1386. (1) Involve a significant increase in amendments proposed to be issued Loca/Public Document Room the probability or consequences of an involving no significant hazards location: Atkins Library Univeristy of accident previously evaluated. The consideration. North Carolina, Charlottee (UNCC change revises the audit frequency of For details, see the individual notice Station). North Carolina 28223. the Station Security Plan from 24 to 12 in the Federal,Registar on the day and NOTICE OF ISSUANCE OF months. The change does not alter plant page cited.This notice does not extend the notice period of the original notice. AMENDMENT TO FACIUTY operations or design and therefore OPERATING LICENSE cannot increase the probability or Arkansas Power and Light Company, consequences of an accident. Docket No. 50-368. Arkansas Nuclear During the period since publication of (2) Create the possibility of a new or One, Unit 2 Pope County, Arkansas the last bl. weekly notice, the different kind of accident from any Commission has issued the following accident previously analyzed because Date ofAmendment Request: April 1. amendments.The Commission has the modification of the audit frequency 1986. determined for each of these for the Station Security Plan does not BriefDescription ofAmendment amendments that the application alter plant design or operations. . Technical Specification changes to complies with the standards and (3) Involve a significant reduction in a allow replacement of a bank of the requirements of the Atomic Energy Act margin of safey because the audit station batteries during the fifth of1954, as amended (the Act), and the frequency change does not affect the refuehng outa e. . Commission's rules and regulatibns. The basis for any Technical Specification or Date pfPub ication oflndividual Commission has made appropriate the safety analysis in the Updated Final Notice in Fedem/ Register: June 10.1986 findings as required by the Act and the Safety Analysis Report. [51 FR 21032). Expimtion Date ofIndividua/ Notice: Commission's rules and regulations in to - The Commission has provided CFR Chapter I, which are set forth in the examples of changes that constitute no I" "'""***"**"* significant hazards consideration in' c'a$blic Document Room Notice of Consideration ofIssuance of Location:Tomlinson L!brary Arkansas Amendment to Facility Operating Federal Register Volume 48, page 14870. Tech University, Russellville, Arkahsas Example (i) consists of a purely License and Proposed No Significant 72801' administrative change to Technical liazards Consideration Determination Specifications and example (vii) Arkansas Power and Light Company, and Opportunity for Hearing in consists of a change to make a license Docket No. 50-368, Arkansas Nuclear connection with these actions was confrom to changes in the regulations. One, Unit 2 Pope County, Arkansas published in the Federal Register as The proposed change is similar to Date of Amendment Request: June 9. indicated. No request for a hearing or example (i)in that it corrects and

• 1986, petition for leave to intervene was filed administrative inconsistency between 10 BriefDescription of Amendment: following this notice.

CFR 73.40(d) and the Technical Changes to Technical Specification 3/ Unless otherwise indicated. the Specifications. The proposed change is 4.10. " Specific Test Exception- Commission has determined th'at these also similar to example (vii) in that the Shutdown Margin to allow surveillance amendments satisfy the criteria for change will make the license conform to of Control Element Assemblies not fully categorical exclusion in accordance 10 CFR 73.40(d). inserted in the core to be performed with 10 CFR 51.22. Therefore, pursuant Accordingly, the Commission within seven days prior to the tests to 10 CFR 51.22(b), no environmental proposes to determine that the change ihstead of within 24 hours prior to'the - impact statement or environmental does not involve a significant hazard tests. . assessment need be prepared for these consideration. Date ofPublication ofIndividual amendments. If the Commission has LocalPublic Document Room Notice in FedemiRegister: June 20,1986 prepared an environmental asseesment location: Swem Library, College of (51 FR 22584). under the special circumstances William and Mary, Williamsburg. Expimtion Date ofIndividualNotice: provision in 10 CFR 51.12(b) and has Virginia 23185. July 21,1986. made a determination based on that Attorney for licensee: Mr. Michael W, LocalPublic Document Room assessment,it is so indicated. Maupin, flunton and Williams Post Location:Tomlinson Library Arkansas For further details with respect to the Office Box 1535. Richmond, Virginia Tech University.Russellville, Arkansas action see (1) the applications for 23213. 72801. amendments, (2) the amendments, and

25774 Fedoest Register / Vol 51. No.136 / Wednesday, hdy 16. 1986 / Notices (3) th2 Commission's related letters. Facility Opemring License Nos.DPR- No sigmficant hazards consideration Safety Evaluations and/or 53 andDPR-69. Amendmenta revised comments received: No. Environmental Assessmenta as the TechnicalSpecifications. LocalPublic DocumentRoom indicated. Allof these items are Date ofinidalnoticain federal location: Southport. Brunswick County availtble for public inspection at the Register: May 7.1986(51 FR16919 at Library,100 W. Moore Street. Southport. Commission's Public Document Room. 16920). North Carolina 28461. 1717 H Street. NW., Washmsten. DC. The Commission's related evaluation and at the local public document reoms Duke Poww Campany, et al., Docket of theamendmentais containedina Nos. 50-413 and 50-414, Catawbe for the particular facilitiesinvolved. A Safety Evaluation dated June 30.1988. copy cf items (2) and (3) may be No significant hazards consideration Nuclear Station. Units 1 and 2. York obt ined upon request addressed to the comments received: No. County,SouMadna . U.S. Nuclear Regula tory Commission. LocalPublic DocumentRoom ' Date ofapplication for amendment: Wcshington,DC20566. Attention: location: Calvert County Library. Prince May 5.1986. Director. Division of Licensing. Frederick. Maryland. Briefdescription of amendment:The Ark nsas Power & Light Company. amendments extend on a one. time basis. Bostoa Edison Company,Dockat No.50-Docket No.56-368, Arkansas Nuclear 293, Ptigrim Nuclear Power Station, by a maximum of three months, certam 1 One, Unit. Pope County, Arkansas Pipnouth, Massachusena surveillance requirements and,by a maximum of four months, the mspect,on i Date of ApplicationforAmendment: Date of applicationforamendment oieach diesel generator. November 27,1965. February 25,1986. Date ofissuance: July 3.1986. BriefDescription ofAmendment:%e Briefdescription of amendment %e Effective date: July 3.1986. amIndment revised the Technical amendment changes theTechnical Sp1cifications to add requirements Amendment No.:8and1. Specifications by updating the 7,cjfjfy op,y,j,ggje,,,, y,,, ypg_ rzlit:d to radiation momforing of the references to Amencan Societyof 35 and NPF-51 Amendments revised HVAC exhaust for the new Low-Level Testing and Materials standarde for the Technical Specifications' Rtdw:ste Storage Build ng. diesel fueloil - . ffate. ly 31 #' # ay 21.1

       // ct Amendment No.:74 y,            y,'i a       date R st                         (51 FR 1 05)

The Commission s related evaluation g facility Opemting Ucense No. NPF-6: f the amendment is containedin a Am:ndment revised the Technical

                                                      *        ' "f No. 9e-
                                                                                           ' Safety Evaluation datedluly 3,1986.

Faciity Opemting License No.DPK- No algnhnt hazarda considerstion Specifications. 35. Amendment revised theTechnical Data ofInitia/ Notice in Fedemt comments received:No. Sp a Register: March 12.1986(51 FE 8588) ,yg, jg LocalPublic Document Room Tha Commission's related evaluation of locaimir musk wouty Ubrary,138 East R t , 51 tha amendmem is evntainedin e Safety Black Street. Rock HiiL South Carolina Evaluafed dated uly7.1986. kn 297 n of the amendmentis containedin a Safety Evaluation dated July 1.1986- Duquesne Light Company, Docket No. corr s ved N LocalPtiblicDbemnentRoonr No significant hazarda consideration 50-334 Beaver Valley Power Station, Locatiort:TomlinamtLibrary. Arkansas comments received: No. Unit No.1. Shippingport, Pennsylvania Tech University,RusseHville Arkansr.s LocalPublic Document Roorn location: Pl) mouth Public Library, u Date of applicationfor amendment 7:so;* North Stseet Plymouth.)A---%2m january 24,1986. Baltimore Can & ElectricCompany. 02360. Briefdescription of amendment:%e Docket Nos.50-317 and 5Hla, Calvest amendment changes the Technical ClifD Nuclear Powee Plant. Unit Nos.1 Camlina Powee & UgWmnpany. Specifications for Beever Valley Unit Docket Noe 50-325and5 Mad, cnd 2 Calvert County, Maryland No.1.to clarify the Modes 5 and 6 Brunswick Steam Electric Plant. Unital chargmg pump survetig, ace Date of qppfestion flor amaaneenest" and 2. Brunswick County, North Partial responso completing eetwre o requiremenes. Only the charging pump is Cedi&e capable ofinadvertently a pplicstions dated December 22,1983 and October 25,1985 se suppismented Date af applicationforamendmear: overpressurizing the reacter vessel: the by Iztter dated April 21.198a. December 10.198&. suryctllance specificationis thue Brief description of amendm*='=-%e Briefdescriptica of amendment:The clarified to refer only to the charging amindments changed the Unitt and amandasanta change the Technical pump. nowher pumps. Unit 2 Technical Specifications (TS) an. Specifications (TS) by clarifying the Date ofdpavence:Jime 24,1986. follows: (a) A prevision is s&tsd tats operability requirementa for the cera Effective date: June 24,1986. 3.6.5.1." Combustible Cao Control. spray systam. Amendment Nar 103. Hydrogen Analyzers." to allow the Data cf!==..=:!=c E199S. ncilly caperi; ting Licang Na ch nging of operatie=al Modes witie Effective date: June 20,1988- . DPR-66. Amanda=* revised the inopesable hydrogen ano6ysers D.44 not. Amendment No.:9&and12&' 'Ibchnical Specifications, l applicable). (2) the reporting Facility Operstag LicenseNos.DPR- Date ofinitialvoticein Federal requirements of TS 4.4.5,5. " Reports. 71 andDPR-62. Amendments added a Register: March 12.1986 (51 FR 8590J Strzrn Generators" are clarified, and p) licensa conditica* The Commission's related avaluation a nsw TS 3/4.4.13. "Rascior Coolant Date ofinitialnotice in Federsk of the amendment is contained in a Syst:m Vents" is incorporated la the TS. Register: January 29619es(51 FR 3710) Safety Eva!uation dated June 24,1986. Date ofissuance: lune 30.1986 The Commission *a related evaluation Effectivedate; luna 30.198& of theamendmentlacantaimedina No sigmficant trazards consideration Amendment Nos;119 and 101. Safety Evaluation dated June 20,1988. comments received: No. ( .

Federal Register / Vol. 51, Nb.136 / Wednesday, July 16, 1986 / Notices _ 25775 LocalPublic Document Room LocalPublic Document Room Northern States Power Company, location: B. F. Jones Memorial Ubrary, location: Appling County Public Library, Docket No. 50-263. Monticello Nuclear 663 Franklin Avenue. Aliquippa. 301 City Hall Drive, Baxley, Georgia. Generating Plant, Wright County, Pennsylvania 15001. Ennes ta Georsia Power Company Oslethorpe Duquesne Ught Company, Docket No. Power Corporation, tviunicipal Elm.tric . Dute ofopp// cation for amendmeat: 50-334. Beaver Valley Power Station. Authority of Georgia, City of Dalton, September 24,1982. Unit No.1. Shippingport, Pennsylvania Ge argia Docket No. 50-321. Edwin L Brief description of amendment '!he Date of applicationfor amendment: Hatch Nuclear Plant, Unit No.1, Appling amendment revises the Technical February 5,1986 County, Georgia Specifications to reflect the installation Briefdescription of amendment:The Date ofapplicationforamendment: I

                                                                                                ,   eg A t grnate, 8od,g,I, ,,,

ecti0n ( t ta show amendment changes the Technical July 26.1985. Specifications for Beaver Valley Unit Briefdescription of amendment:The the normal position of the recirculation No.1 to revise the reporting loop sample valves. Ametidment No.42 amendment revises the Technical dated March 27,1986 revised Sections rzquirements on reactor coolant specific Specifications to add a specification and d b activity from "Special Report" to table, addressing component cyclic and (Of ,*" ten Annual Report, and to delete an transient limits. I su e et n 3 6.G.3 was action statement regarding limits on not deleted.This amendment also Date ofissua.;ce: June 26,1986. includes revised page 129 with operation when radioiodine levelis Effective date: June 26,1983, and shall greater than 1 uCi/gm in the primary subsection 3.6.G.3 deleted. This be implemented within 60 days, amendment resolves items 1 and 10 of coolant. both These changes are in Amendment No.:128. ' this application. Item Nos. 2. 3,4. 5. 6,8 accordance with NRC Generic Letter 85- Facility Operating Ucense No. DPR-19-and 11 were resolved in Amendment

57. Amendment revised the Techrical Nos. 32 (5/28/85).12 (11/30/82) 22 (2/2/

Date ofissuance: June 24,1986. Specifications. 84) 17 (4/18/83) 42 (3/27/86),36 (12/23/. Effective date: June 24,1986. Date ofinitialnotice in Federal 85) and 41 (3/24/86) respectively. Item Amendment No.102. Register: August 28,1985 (50 FR 34941). No. 7 was withdrawn and item No. 9 is facility Opemting Ucense No. DPR- The Commission's related evaluation under staff review.

66. Amendment revised the Technical of the amendment is contained in a' Date ofissuance: July 1.1986.

Specifications. Safety Evaluation daled June 26,1986. Effective date: July 1,1986. Date ofinitialnotice in Federal No Significant hasants considention Amendment No.:45. Register: March 12,1986 ($1 FR 8590). comments received:No. Facility Opemting Ucense No. DPR-The Commission's related evaluation LocalPublic Document Room 22. Amendment revised the Technical of the amendment is contained in a location: Appling County Public Library, Specifications. Safety Evaluation dated June 24.1986., 301 City Hali Ddve Basuey, Geursia No significant hazards consideration 31513. Date ofinitialnotice in Federal Register: October 26,1983 (48 FR 40589), comments receive: No. Indian and Michigan Electric Company, and June 20,1984 (49 FR 25365). The LocalPublic Document Room Docket Nos. 56,315 and 56-315 Donald Commission's related evaluation of the location: B. F. Jones Memorial Library' C. Cook Nuclear Plant Unit Nos.1 and amendment is contained in a Safety 663 Franklin Avenue, Aliquippa, 2. Berrien County, Michigan Evaluation dated July 1,1986. Pennsylvania 15001. No Significant hazards consideration

                                                           #I#p cation for amendments:       comments received: No.

Georgia Power Company Oglethorpe y 4g Power Corporation Municipal Electric LocalPublic Document Room I #'# ## ' Authority of Georgia, City of Dalton, location: Environmental Conservation t al Libr'ary, Minneapolis Public Library,300 I Georgia, Docket No. 50-321. Edwin L (,'c ficat ons to change the HVAC Nicollet Mall. Minneapolis, Minnesota ( llatch Nuclear Plant, Unit No.1. Appling Charcoal Filter Fire Suppression County, Georgia 55401. Systems to a manual mode of operation Data of applicationfor amendment: as a means to prevent undetected Northern States Power Company, January 7,1985. leakage of water on the filters and filter Docket No. 50-263, Menticello Nuclear Briefof description of amendment: failure. ~ Generating Plant. Wright County, The amendment revises reactor vessel Date ofissuance: June 30,1986. Minnesota operating temperatute and pressure Effective date: lune 30'1986. Date of application for amendment: I limits and to intake associated editorial Amendment Nos. s7 and 84. September 14,1984, and clarified on changes. Facility Opemting Ucense Nos. DRP- January to and May 7.1986. Date ofissuance: lune 20.1986. 58andDPR-74. Amendments revised Briefdescription of amendment:The Effective date; june 20,1986. the Technical Specifications. amendment reflects the changes in the Amendment No. 126. Date ofinitia/ notice in Federal revised section of 10 CFR 50.72. and a facility Opemting Ucense No. DPR- Register: May 7,1986 (51 FR 16929) new section,10 CFR 50.73, both of which

57. Amendment revised the Technical The Commission *r, related evaluation became effective on ranuary 1.19n The Specifications. +

of the amendment is contained in a revised subsection 50.72 modifies the Date ofinitia/ notice in Federal Safety Evaluation dated June 30,1986. immediate notification requirements for Register: March 26,1986 (51 FR 10460). No significant hazards consideration operating nuclear power reactors and The Commission's related evaluation comments received: No. subsection 50.73 provides for a revised of the amendment is contained in a LocalPublic Document Room Licensee Event Report System. The Safety Evaluatica dated lune 20.1986.- location:Maude Preston Palenske amendment tIso includes changes to No significant hazards consideration Memorial Library,500 Market Street. St. Table 6.1.1. " Minimum Shift Crew comments received: No. Joseph. Michigan 49085. Composition" to comply with the

25U6, Federal Register / Vol. 51. No.136 / Wednesday. July 16,1986 / bices , requirementa of 10 CFR 50.54(m)(2). hs Date ofissacacer juna 12.1986. Facility OpemtingLicenseNos: NPF-addition, organizational changes include Effective date Jane 12.198& 10 andNPF-15: Amendments revised two position title changes and a new Amendment No.15. the Technical Specifications. position of Assistant Plant Manager. Facility Operating License No.DPR- Date ofinitialNoticein Federal Date ofissuance: July 1.1986. 18. Amendment revised the Technical Register: May 21,1986 (51 FR 18805). N Effectne date: July 1,1986. Specifications. Commission's related evaluation of tha Amendment No:46. Date ofinitialnoticein Federal amendments La contained in a Safety Facdity Cy 4 Licasse No.PPR- Register: October 26; 1983 (48 FR 49595). Evaluation dated June 25,1986.

22. Amendment revised theTechsaca4 W Cormmesion'e refated evaluation No significant hasards considered Specifications. of the amendment is contained in a comments were received: No.

Date ofinitialnoticeie Federal Sa fety Evaluatnon dated lune 12.1986 LocalPublic Document Room Register: September 25.1986(5e FR No significant hazards conside ation Location: General Library. University of 38917). commenta received

• No. California at Irvine hvine. California

    & Commission'srelated evalentson              LocalPublicDocumentRoom                    92713.

of theamendamentiscastainedina Location: Rochester Public Library.115 Safety Evaluation dated fuly 1.198k South Avenue. Rochester New York Vermont Yankee Nuclear Power No significant hazards consideration 14610. Corporation. Docket No. 56-271, comments received:Not Vermont Yankee Nuclear Power Station. Southm Califmia Edisco Capeny, et Vernon, Vermont LocalPubli.c Document Roon, alDecket Nos. 50-361 and 50-3es. Saa location: Environmental Conservation Date of application foramendment: Library. Minnee polis Public Library 300 Onofre Nuclear Generating St=Han Units 2 and 3. San Diego County, May 10.1965, as supplemented NicolletMall. Minneapolis Minnesots November 21,1985. 55401. Califmia Brief description of amendment:The Omahe PubBe PowerDistrict. Docket 08#88 8I8FPli C8#i888[# amendment revised the Technical

                                               "            ' ^"                      ~

Specifications to accommodate shifts in No. 56-285. Fort Calhoun Station. Unit B efdesc p o of a e tcThe Ns.1. Washington County Nebraska transm,on temperatm & mactw amendments revise Technical " Date ofapplication for amendmes1: Specification Table 3.8-1. " Containment $'((d by radia April 9.1986. da nage The e Penetration Canductor Overturrent shifts were accounted for by revision of Briefdescription of amendment:N Protective Devices." to correct the plant pressure-temperature limita for amendment incorporated operability equipment designationa and Technical and surveillance requirements for new heating up and cooling down the reacter Specification 4.3.3.2.a to stata that a fire suppression eqmpmentin the vessel. Periodic review and adjustment, channel check ra not needed in the case if necessary of the curves to account for compressor room. of a temporary loss of the plant Date ofissuance: July 1.1986. the effects of irradiation are required by computer. Effective date:Tuly1.1986 10 CFR Part 50. Appendices G and H. Date ofissuance: June 20,1986. Amendment No.:98 . Effe~ctive date: lune 20.1988. Date ofissuance: lune 24.M FacilityOiperating License & DPl%- AmendmentNos:49 and 38. Effective date: lune 24.1986.

40. Amendment revised theTechnical Facility Opemting LicenseNos. NPF- Amendment No.:93.

Specifications. 10 andNPF-15. Amendment revised tha facility Operating License No. DPR-Date ofinitialnoticein Federal Technical Specifications. 28# Register: May 7,1986 (51 FR 16032). Date ofinitialsotice in Fedemj Date ofinitia/ notice m Federal Th2 Commission *a related evaluation Register: April 23,1985 (50 FR 18015). Registser: September 25.1985 (50 FR of the amendment is sontained in a The Commiaminn's related evaluation 3a923), The November 21.1985 submittal Szfzty Evaluation dated July 1.1981L of the amendments is en*ht in a provided clarifying information and Na significant hazards consideration Safety Evaluation dated June 20.19886 therefore did not change the findings of comments received: No. No significant hazarda consideration the initial Federal Register notice. The LocalPublic Document Room comments were receivediNo. Commission's related evaluation of the Located: W. Dale Clark Library. 215 LocalPbblicDocumentRoam amendment is contained in a Safety l South 15th Street. Omaha. Nebraska Locatiom General Library University cf Evaluation dated June 24.1986. 68102- California at Irvine. Irvine. California Ne egnificant hW3 cenddMan Rochester Gas and Electric Corposeaisen, 92713- comments received: No. LocalPublic Document Room Dock t No. 50-244. R. E. Ginna Nuclear Southern California FAmen t'nsepany,og P2wer Plant. Wayne County, New York location: Brooks Memorial Library. 224 al., Docket Naa, so-aat and 56-aea. San Main Street. Brattleboro Vermont 05301. Date of applicatianforasundment: Onotre Nuclear T ' _ _ Stathoa, Decimber 8.1982 supplemented Octobee Units 2 and3, San Diego County, Wiscnnsin Electric Power Coaipany. 10.1983. August 861964,and August 19. California Docket Nos. N and SS-ast Point 1985. **** ' * ***** Iktes ofAnnlicantofAmend>nents- Town Mm Cuoeks. Manitowc Brief description ofamendment:% February 7.1'98e. amendment changes the Technical BriefDescriptam of Amendmentarh County, Wisconsis Specifications to extend the reactor amendments revise Technical Date of application for amendments-vessel pressure-temperature limita front Speci5caticu 3/4A7."RCS Specific May 8,1986. 10E to 21.0 effective full power years Activity" in accord ==ca wtiir NEC Brief description of amendmentsr The (EFPY) and permits withdrawaIof the Generic Letter 85-19. amendments revise limiting condition next reactor vessel surveillance capsula Date offsaucace: June 25,19ee6 for operation (LCO) for the component at 17 EFPY as a result of the analysisof Effective Data: june 2561988, to be cooling water (CCW) systena to permit a the reactor vessel surveiltance capsule implemented withia.3e daye as insa====.. component cooiing weier heat T. Amendment Nos.:50 and 3a. exchanger to be out of service for up to

i Federal Regleter / Vol. 51. No.136 / Wednesday. July 16. 1986 / Notices 25777 five days between the period of July 1 to September 30,1986. This change allowa replacement of existing heat exchangers and the installation of an additional hsat exchanger. Date ofissuance: June 25.1986. Effective date: Upon issuance. AmendmentNos.:101 and 104. Facility Operating Lice.nse Nce. DPR-24 andDPR-27. Amendments revised the Technical Specifications. Date ofinitialnoucela Federal Register: May 21.1986 (51 FR 18806). The Commission's related evaluation cf the amendments is contained in a Safety Evaluation dated June 25.1980. No significant hazards consideration c:mments received: LocalPublic Document Room location: Joseph P. Mann Library.1816 Sixteenth Street.Two Rivers. Wisconsin. Dated at Bethesda. Maryland this 10th day cf July 1988. For the Nuclear llegulatory Commiselon. R. Wayne Houston. Acting Dimetor Divleion ofBM !.icorneim Office ofNuclearReactorRegulatiorn. [FR Doc. 86-15017 Filed 7-tm 8:45 am] sounes cooe rsee.sw l (}}