ML071450234

Issuance of License Amendment 145 Scram Discharge Volume Vent and Drain Valves

ML071450234
Person / Time
Site:	Perry
Issue date:	06/22/2007
From:	Wengert T J NRC/NRR/ADRO/DORL/LPLIII-2
To:	Allen B S FirstEnergy Nuclear Operating Co
Wengert, Thomas NRR/DORL 415-4037
Shared Package
ML071450238	List: ML071450234 ML071770466
References
TAC MD3898
Download: ML071450234 (15)

Text

June 22, 2007Mr. Barry S. AllenSite Vice President FirstEnergy Nuclear Operating Company Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097

SUBJECT:

PERRY NUCLEAR POWER PLANT, UNIT NO. 1 - ISSUANCE OFAMENDMENT RE: SCRAM DISCHARGE VOLUME VENT AND DRAIN VALVES (TAC NO. MD3898)

Dear Mr. Allen:

The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosedAmendment No. 145 to Facility Operating License No. NPF-58 for the Perry Nuclear Power Plant, Unit No. 1. This amendment revises the Technical Specifications (TSs) in response to your application dated December 29, 2006.This amendment modifies the TS requirements for scram discharge volume vent and drainvalves.A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in theCommission's next biweekly Federal Register notice.Sincerely,/RA/Thomas J. Wengert, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-440

Enclosures:

1. Amendment No. 145 to NPF-58 2. Safety Evaluationcc w/encls: See next page June 22, 2007Mr. Barry S. Allen Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081

SUBJECT:

PERRY NUCLEAR POWER PLANT, UNIT NO. 1 - ISSUANCE OFAMENDMENT RE: SCRAM DISCHARGE VOLUME VENT AND DRAIN VALVES (TAC NO. MD3898)

Dear Mr. Allen:

The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosedAmendment No. 145 to Facility Operating License No. NPF-58 for the Perry Nuclear Power Plant, Unit No. 1. This amendment revises the Technical Specifications (TSs) in response to your application dated December 29, 2006.This amendment modifies the TS requirements for scram discharge volume vent and drainvalves.A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in theCommission's next biweekly Federal Register notice.Sincerely,/RA/Thomas J. Wengert, Project ManagerPlant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-440

Enclosures:

1. Amendment No. 145 to NPF-58 2. Safety EvaluationDISTRIBUTION

PUBLICLPL3-2 R/FRidsNrrPMTWengertRidsNrrDirsItsb RidsOgcRpRidsNrrLAEWhittRidsRgn3MailCenterRidsNrrDorlLpl3-2 RidsAcrsAcnwMailCenterRidsNrrDorlDprGHill (2)Package Accession Number: ML071450238Amendment Accession Number: ML071450234 TS Accession Number: ML*See SE dated**NLOOFFICELPL3-2/PMLPL3-2/LADIRS/ITSB*OGC**LPL3-2/BCNAMETWengertEWhittTKobetzBKlukanRGibbsDATE6/22/07 6/22/07 2/20/07 6/11/07 6/22/07OFFICIAL RECORD COPY Perry Nuclear Power Plant, Unit No. 1 cc:David W. Jenkins, AttorneyFirstEnergy CorporationMail Stop A-GO-1576 South Main StreetAkron, OH 44308Resident Inspector's OfficeU.S. Nuclear Regulatory CommissionP.O. Box 331Perry, OH 44081-0331Regional Administrator, Region IIIU.S. Nuclear Regulatory Commission2443 Warrenville Road, Suite 210Lisle, IL 60532-4531Sue HiattOCRE Interim Representative8275 MunsonMentor, OH 44060Manager, Site Regulatory ComplianceFirstEnergy Nuclear Operating CompanyPerry Nuclear Power PlantMail Stop A-PY-A200P.O. Box 97, 10 Center RoadPerry, OH 44081-0097Mayor, Village of North PerryNorth Perry Village Hall4449 Lockwood RoadNorth Perry Village, OH 44081Donna Owens, DirectorOhio Department of CommerceDivision of Industrial ComplianceBureau of Operations & Maintenance6606 Tussing RoadP.O. Box 4009Reynoldsburg, OH 43068-9009Carol O'Claire, Chief, Radiological BranchOhio Emergency Management Agency2855 West Dublin Granville RoadColumbus, OH 43235-7150Mayor, Village of PerryP.O. Box 100Perry, OH 44081-0100 Dennis ClumRadiological Assistance Section SupervisorBureau of Radiation ProtectionOhio Department of HealthP.O. Box 118Columbus, OH 43266-0118Zack A. Clayton DERROhio Environmental Protection AgencyATTN: Mr. Zack A. ClaytonP.O. Box 1049Columbus, OH 43266-0149ChairmanPerry Township Board of Trustees3750 Center Road, Box 65Perry, OH 44081Daniel Z. FisherTransportation DepartmentPublic Utilities Commission180 East Broad StreetColumbus, OH 43215-3793 James H. LashSenior Vice President of Operations and Chief Operating OfficerFirstEnergy Nuclear Operating CompanyMail Stop A-GO-1476 South Main StreetAkron, OH 44308Director, Fleet Regulatory AffairsFirstEnergy Nuclear Operating CompanyMail Stop A-GO-276 South Main StreetAkron, OH 44308Joseph J. HaganPresident and Chief Nuclear OfficerFirstEnergy Nuclear Operating CompanyMail Stop A-GO-1476 South Main StreetAkron, OH 44308 Perry Nuclear Power Plant, Unit No. 1 cc:

Danny L. Pace Senior Vice President, Fleet EngineeringFirstEnergy Nuclear Operating CompanyMail Stop A-GO-1476 South Main StreetAkron, OH 44308Jeannie M. RinckelVice President, Fleet OversightFirstEnergy Nuclear Operating CompanyMail Stop A-GO-1476 South Main StreetAkron, OH 44308Manager, Fleet LicensingFirstEnergy Nuclear Operating CompanyMail Stop A-GO-276 South Main StreetAkron, OH 44308Richard AndersonVice President, Nuclear SupportFirstEnergy Nuclear Operating CompanyMail Stop A-GO-1476 South Main StreetAkron, OH 44308 FIRSTENERGY NUCLEAR OPERATING COMPANYFIRSTENERGY NUCLEAR GENERATION CORP.OHIO EDISON COMPANYDOCKET NO. 50-440PERRY NUCLEAR POWER PLANT, UNIT NO. 1AMENDMENT TO FACILITY OPERATING LICENSEAmendment No. 145 License No. NPF-581.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for license filed by FirstEnergy Nuclear Operating Company,et al., (the licensee) dated December 29, 2006, complies with the standards andrequirements of the Atomic Energy Act of 1954, as amended (the Act), and theCommission's rules and regulations set forth in 10 CFR Chapter I;B.The facility will operate in conformity with the application, the provisions of theAct, and the rules and regulations of the Commission;C.There is reasonable assurance (i) that the activities authorized by thisamendment can be conducted without endangering the health and safety of thepublic, and (ii) that such activities will be conducted in compliance with theCommission's regulations;D.The issuance of this amendment will not be inimical to the common defense andsecurity or to the health and safety of the public; andE.The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied.2.Accordingly, the license is amended by changes to the Technical Specifications asindicated in the attachment to this license amendment, and paragraph 2.C.(2) of FacilityOperating License No. NPF-58 is hereby amended to read as follows: (2)Technical SpecificationsThe Technical Specifications contained in Appendix A and the EnvironmentalProtection Plan contained in Appendix B, as revised through Amendment No. 145 are hereby incorporated into this license. FENOC shall operate thefacility in accordance with the Technical Specifications and the EnvironmentalProtection Plan.3.This license amendment is effective as of its date of its issuance and shall beimplemented within 90 days of the date of issuance.FOR THE NUCLEAR REGULATORY COMMISSION/RA/Russell Gibbs, ChiefPlant Licensing Branch III-2Division of Operating Reactor LicensingOffice of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Facility Operating LicenseDate of Issuance: June 22, 2007 ATTACHMENT TO LICENSE AMENDMENT NO. 145FACILITY OPERATING LICENSE NO. NPF-58DOCKET NO. 50-440Replace the following pages of the Facility Operating License and Appendix A TechnicalSpecifications with the attached revised pages. The revised pages are identified byamendment number and contain marginal lines indicating the areas of change. Remove InsertLicense NPF-58License NPF-58Page 4Page 4

TS TS3.1-243.1-24 renewal. Such sale and leaseback transactions are subject to the representationsand conditions set forth in the above mentioned application of January 23, 1987,as supplemented on March 3, 1987, as well as the letter of the Director of theOffice of Nuclear Reactor Regulation dated March 16, 1987, consenting to suchtransactions. Specifically, a lessor and anyone else who may acquire an interestunder these transactions are prohibited from exercising directly or indirectly anycontrol over the licenses of PNPP Unit 1. For purposes of this condition thelimitations of 10 CFR 50.81, as now in effect and as may be subsequentlyamended, are fully applicable to the lessor and any successor in interest to thatlessor as long as the license for PNPP Unit 1 remains in effect; these financialtransactions shall have no effect on the license for the Perry Nuclear facilitythroughout the term of the license. (b)Further, the licensees are also required to notify the NRC in writing prior to anychange in: (i) the terms or conditions of any lease agreements executed as part ofthese transactions; (ii) the PNPP Operating Agreement; (iii) the existing propertyinsurance coverage for PNPP Unit 1; and (iv) any action by a lessor or others thatmay have an adverse effect on the safe operation of the facility.C.This license shall be deemed to contain and is subject to the conditions specified inthe Commission's regulations set forth in 10 CFR Chapter I and is subject to allapplicable provisions of the Act and to the rules, regulations, and orders of theCommission now and hereafter in effect; and is subject to the additional conditionsspecified or incorporated below:(1)Maximum Power LevelFENOC is authorized to operate the facility at reactor core power levels not inexcess of 3758 megawatts thermal (100% power) in accordance with the conditionsspecified herein.(2)Technical SpecificationsThe Technical Specifications contained in Appendix A and the EnvironmentalProtection Plan contained in Appendix B, as revised through Amendment No. 145,are hereby incorporated into the license. FENOC shall operate the facility inaccordance with the Technical Specifications and the Environmental Protection Plan.(3)Antitrust Conditionsa. FirstEnergy Nuclear Generation Corp. and Ohio Edison CompanyAmendment No. 145 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. 145 TO FACILITY OPERATING LICENSE NO. NPF-58FIRSTENERGY NUCLEAR OPERATING COMPANYFIRSTENERGY NUCLEAR GENERATION CORP.OHIO EDISON COMPANYPERRY NUCLEAR POWER PLANT, UNIT NO. 1DOCKET NO. 50-44

01.0INTRODUCTION

By letter to the U.S. Nuclear Regulatory Commission (NRC, the Commission) datedDecember 29, 2006, FirstEnergy Nuclear Operating Company, et al. (the licensee) requestedchanges to the technical specifications (TSs) for the Perry Nuclear Power Plant (PNPP), UnitNo. 1. The proposed changes would revise the TS requirements for scram discharge volumevent and drain valves. Specifically the proposed changes would revise the required actionwithin TS 3.1.8, ?Scram Discharge Volume (SDV) Vent and Drain Valves" for the condition ofhaving one or more SDV vent or drain lines with one valve inoperable. These changes arebased on Technical Specifications Task Force (TSTF) Change Traveler No. 404 (TSTF-404),?Scram Discharge Volume Vent and Drain Valves" Revision 0, that has been approvedgenerically for Boiling Water Reactor 6 (BWR/6) Standard Technical Specifications (STS),contained in NUREG-1434, "Standard Technical Specifications General Electric Plants, BWR/6Specifications," Revision 2. A notice announcing the availability of this proposed TS changeusing the consolidated line item improvement process (CLIIP) was published in the FederalRegister on April 15, 2003 (68 FR 18294).

2.0REGULATORY EVALUATION

NRC regulations and review standards such as Appendix A, ?General Design Criteria forNuclear Power Plants," to Title 10 of the Code of Federal Regulation (CFR) Part 50, includespecific requirements for reactor protection and reactivity control systems. The reactorprotection systems for BWRs use a hydraulic system to insert control rods into the reactor core. During an actuation of the reactor protection system (a scram), water is exhausted from thecontrol rod drive mechanisms to the SDVs. Proper maintenance and operation of the SDVs interms of instrumentation and limiting water volumes are essential for assuring the reliability ofthe reactor protection system (see NRC Bulletin 80-17, ?Failure of Control Rods to Insert DuringA Scram at a BWR," related Orders to specific facilities, and information provided in plant finalsafety analysis reports and TS Bases). Maintaining the SDVs to ensure that accumulated waterdoes not hamper or slow the insertion of control rods requires vent and drain valves. The ventand drain valves isolate during a scram to limit the amount of coolant discharged so thatadequate core cooling is maintained and offsite doses remain within regulatory limits. Specific license requirements for SDV vent and drain valves are defined in TS 3.1.8. Theexisting Limiting Condition for Operation (LCO) 3.1.8, requires that each SDV vent and drainvalve be operable. The operability of all SDV vent and drain valves ensures that the SDV ventand drain valves will close during a scram to contain reactor water discharged to the SDVpiping. Since the vent and drain lines are provided with two valves in series, the single failure ofone valve in the open position will not impair the isolation function of the system. Additionally,the valves are required to open on scram reset and during plant operation to control the amountof water accumulating in the SDV.If one or more SDV vent and drain lines have a single valve that is inoperable, the existingrequired action is to restore the valve(s) to operable status within 7 days. If an inoperable valveis not restored to operable status, a plant shutdown to MODE 3 is required within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Ifone or more SDV vent or drain lines have both valves inoperable, the associated line must beisolated within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. In this condition, the plant is allowed to operate indefinitely. A noteassociated with the required action clarifies that the valves may be opened under administrativecontrols to allow draining of the SDV. The existing SDV vent and drain valve required actionsare inconsistent in that, although the operational and safety concerns are similar for having oneor both valves in a line being inoperable, the actions for a single inoperable valve do not allowfor the isolation of the line and administrative controls to support the draining of the SDV.The proposed change would revise the required actions to be more consistent with the safetysignificance of one inoperable valve in a SDV line versus two inoperable valves in an SDV line.

3.0TECHNICAL EVALUATION

3.1Proposed TS ChangeThe proposed changes to TS 3.1.8 are:1.Required Action A.1 is revised from restoring the single inoperable SDV vent anddrain valve in one or more SDV vent and drain lines to operable status to isolatingthe associated line.2.The Note to Required Action B.1, which allows an isolated line to be unisolatedunder administrative controls for the purpose of draining and venting the SDV, ismoved to a note that applies to both Conditions A (single inoperable valve) and B(both valves inoperable).3.2NRC Staff EvaluationWith one SDV vent or drain valve inoperable in one or more lines, the isolation function wouldbe maintained since the redundant valve in the affected line would perform its safety function ofisolating the SDV. The current ACTION statement allows 7 days to repair the inoperable valve;the proposed change would allow for the isolation of the affected line and continue operation. Ifthe affected line is not isolated within the 7-day time period (or the inoperable valve is notrestored), the licensee would then be required to proceed to MODE 3 in the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Maintaining the 7-day Completion Time is acceptable because of the low probability of theconcurrent events of a scram within the 7 days of the Completion Time and a failure of the redundant valve(s). Alternately, if the inoperable valve was initially closed, there would beample time and a warning available to drain the SDV before an automatic scram wouldoccur due to SDV high level. The allowance to administratively open a line that is isolated to comply with the actions (topermit draining and venting the SDV) is allowed by existing Required Action B.1. Thisallowance is being moved to apply to all ACTIONS based on the change proposed to Action A. This would allow any accumulated water in the line to be drained, to preclude a reactor scramon SDV high level. A reactor scram is initiated if the SDV water level in the instrument volumeexceeds a specified setpoint. The setpoint is chosen so that all control rods are inserted beforethe SDV has insufficient volume to accept a full scram. Regarding the isolation of the SDV, theremaining operable SDV vent and drain valve(s) would close automatically on a scram signal toisolate the lines. Or, if both valves in a line were inoperable (and opened under this provision),the reactor coolant release could be terminated by resetting the scram from the control room, orby manually closing the valves. Resetting the scram automatically closes the scram outletvalves, isolating the control rod drive discharge path to the SDV.3.3Technical Evaluation ConclusionBased on the low probability of an event occurring during the defined Completion Timeassociated with this condition, the subsequent isolation of the affected lines, and the ability toopen and drain the lines before an automatic scram due to SDV high water level, the proposedchange maintains the necessary safety features and is therefore acceptable to the NRC staff. The change to TS 3.1.8 requires that the licensee revise the discussion in the associated Basessection. Although the licensee's application included possible wording for the revised Basesdiscussion for TS 3.1.8, the licensee will formally address the change to the Bases inaccordance with the Bases Control Program or its administrative procedure for revising Bases. The NRC staff does not believe that the Bases change will require prior NRC approval whenevaluated against the criteria of 10 CFR 50.59, "Changes, tests, and experiments," and,therefore, agrees that the revision of the Bases to TS 3.1.8 should be addressed separatelyfrom this amendment and should be included in a future update of the TS Bases in accordancewith the bases Control Program and the licensee's administrative controls.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Ohio State official was notified of the proposed issuance of the amendment. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

This amendment changes a requirement with respect to installation or use of a facilitycomponent located within the restricted area as defined in 10 CFR Part 20. The NRC staff hasdetermined that the amendment involves no significant increase in the amounts, and nosignificant change in the types, of any effluent that may be released offsite and that there is nosignificant increase in individual or cumulative occupational radiation exposure. TheCommission has previously issued a proposed finding that this amendment involves nosignificant hazards consideration and there has been no public comment on such finding (72 FR 11388; March 13, 2007). Accordingly, this amendment meets the eligibility criteria forcategorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), noenvironmental impact statement or environmental assessment need be prepared in connectionwith the issuance of this amendment.

6.0 CONCLUSION

The NRC staff has concluded, based on the considerations discussed above, that: (1) there isreasonable assurance that the health and safety of the public will not be endangered byoperation in the proposed manner, (2) such activities will be conducted in compliance with theCommission's regulations, and (3) the issuance of this amendment will not be inimical to thecommon defense and security or to the health and safety of the public.Principal Contributor: T. Wertz Date: June 22, 2007