L-19-062, Supplement to License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1. Definitions, 5.0., Administrative Controls. for Permanently Defueled Condition

Supplement to License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1. Definitions, 5.0., Administrative Controls. for Permanently Defueled Condition

ML19058A328
Person / Time
Site:	Davis Besse
Issue date:	02/27/2019
From:	Bezilla M FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
EPID L-2018-LLA-0287, L-19-062
Download: ML19058A328 (9)

Text

FENOC 5501 North State Route 2 Oak Harbor, Ohio 43449 Illerk B. Bedlla Yice President - Nuclear February27,2019 L-19-062 4 t9-321-7676 Fax: 4l%321-7582 10 cFR 50.90 ATTN: Document Gontrol Desk U.S. Nuclear Regulatory Commission Washington, DC 20555'0001

SUBJECT:

Davi+Besse Nuclear Power Station, Unit No. 1 Docket No. 50-346, Lioense No. NPF-3 Supplement to License Amendment Reouest - Prooooed Chanoes to Technical Soecifications Sections 1.1.'De{inilions.'and 5.0.'Administrative Controls."for Permanentlv Detueled Condition (EPID No. L-20 1 8-LLA-0287)

By letterdated October 22,2018 (Accession No. ML18295A289), FirstEnergy Nuclear Operating Company (FENOC) submitted a license amendment request (l.AR) for Davis-Besse Nuclear Povuer Station, Unit No. 1 (DBNPS). The LAR proposed changes to the organization, staffing, and training rcquirements contained in Section 5.0, "Administrrative Controls" of the DBNPS TechnicalSpeciftcations (l-S) and defined two new positions for Certifred Fuel Handbr and Non-Certified Operator in Section 1.1, "Deftnitions," to supportthe transition of DBNPS to a permanently defueled ondition.

On February 13, 201g,the Nuclear Regulatory Commission (NRC) Proiect Manager identified several reoommended changes in the proposed TS pages. The definition of a certified fuel handler should include the' prior to 'provisions," and TS 5.2.2 use of semi-colons and periods should be ionsistent. Based on this feedback, FENOC is providing this supplement to the l3R to incorporate these changes.

Enclosed is the supplemental information in support of the amendment request. The enclosure contains pages of the I.AR afiected by the changes (Page 3 of 22 and Page 6 of 22) and TS page markups for TS pages 1.1-1, 5.2'1, and 5.2-2. These pages supersede the previously provided pages.

FENOC has reviewed the previously provlded conclusion thatthe proposed changes present no significant hazards consideration under the standards set forth in 10 CFR 50.92,'lssuance of amendment." The information provided in this supplement does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration.

Davis-Besse Nuclear Power Station, Unit No. 1 L-19-062 Page2 There are no regulatory commitments contrained in this submittral. lf there are any questions, or if additional information is required, please contact Mr. Thomas Lentz, Manager, FENOC Nuclear Licensing & RegulatoryAffairs, at (330) 315810.

I declare under penalty of perjury that the foregoing is true and correct. Executed on FebruarV 27,2019.

Sincerely,

Enclosure:

Supplementto Lioense Amendment Request Evaluation of Proposed Changes cc:

NRC Region lll Administrator NRC Resident lnspector NRR Projec't Manager Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)

Utility Radiological Safety Board

Enclosure Supplement to License Amendment Request Evaluation of Proposed Changes (6 pages follow)

Enclosure Page 3 of 22 This LAR provides a discussion and description of the proposed TS changes, a technical evaluation of the proposed TS changes, and information supporting a finding of no significant hazards consideration (NSHC).

2.A DETAILED DESCRIPTION contains a markup of the current TS pages. The specific changes affecting TS Sections 1.1 and 5.0 are described in this section;the supporting technica!

evaluation is presented in Section 3.0 of this enclosure. Proposed revisions in this section are shown in Bold-ltalics and deletions are shown using s+rike+hrugh. All revised formatting, numbering, and wording in TS Section 5.0 is consistent with Section 5.0 of Reference 3, except where noted to make the specification germane with a permanently defueled reactor.

TS Section 1.1 - Definitions Current TS Proposed TS

[A term and definition for CERTIFIED FUEL HANDLER is not listed in the current TS.I Term CERTIFIED FUEL HANDLER Definition A CERTIFIED FUEL HANDLER is an individual who complies with the provisions of the CERTIFIED FUEL HANDLER training and retraining program required by Specification 5.3.2.

[A term and definition for NON-CERTIFIED OPERATOR is not listed in the current TS.I Term NON-CERTI FI ED OPERATO R Definition A NON-CERTIFIED OPERATOR is a non-licensed operator who complies with the qualification requirements of Specification 5.3.1, but is not a CERTIFIED FUEL HANDLER.

Enclosure Page 6 of 22 TS Section 5.2 - Organization Current TS Proposed TS Specifications 5.2.2.a and 5.2.2.t for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements;

c. A radiation protection technician shall be on site when fuel is in the reactor.

The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position;

d. Deleted;

e. The operations manager shall either hold or have held a Senior Operator license. The assistant operations manager shall hold a Senior Operator license for the Davis-Besse Nuclear Power Station; and

f. When the reactor is operating in MODE 1, 2, 3, or 4 an individual shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.

This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.

HANDLER;

b. Shift crew composition may be less than the minimum requirement of Specifications 5.2.2.o #or a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements and the following conditions are met:

1) No nuclear fuel movemenfs are in progress;

2) No movement of loads over nuclear fuel is in progress; and

3) No unmanned shift positions during shitt turnover shall be permitted due to an incoming shift crew member being late or absent;

c. A radiation protection technician shall be on site when fuel is in the reaeterduring movement of nuclear tuel and during the movement of loads over nuclear fuel. The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position;

d. Deleted At least one person qualitied to stand watch in the control room (NON-CERTIFIED OPERATOR or CERTIFIED FUEL HANDLER) shall be present in the control room when nuclear fuel is sfo red in the spent fuel pool;

e. The shift manager shall either held er have held a Senier Opera*er+ieens'* be a CERTIFI ED FU EL HANDTEP The assistant ep lieense fer the Davis Besse Nuelear Pewer Statien; and f.

Definitions 1,1 1.0 USE AND APPLICATION 1.1 Definitions The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

Term ACTIONS Definition ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

ALLOWABLE THERMAL POWER AXIAL POWER IMBALANCE AXIAL POWER SHAPING RODS (APSRS)

ALLOWABLE THERMAL POWER shall be the maximum reactor core heat transfer rate to the reactor coolant permitted by consideration of the number and configuration of reactor coolant pumps (RCPs) in operation.

AXIAL POWER IMBALANCE shall be the power in the top half of the core, expressed as a percentage of RATED THERMAL POWER (RTP), minus the power in the bottom half of the core, expressed as a percentage of RTP.

APSRs shall be control components used to control the axial power distribution of the reactor core. The APSRs are positioned manually by the operator and are not trippable.

CenrtrleO rUel Un ies witn tne orovision trainino anO retra CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlappitrg, or total channel steps.

1.1-1 Davis-Besse Amendmenl2Tg I

Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 5.2.2

-td,.

Onsite and Offsite Oroanizations onsiteandotfsiteorganizationsshallbeestabIishedfor@

and corporate managemenlrespeetively. The onsite and offsite organizations shallincludethepositionsforactivitiesatfecting@

Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all eperatinglagi[ft organization positions. These relationships shall be documented and updated, as appropriate, in organization cha*sdggggdions, functionaldescriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements, including the plant-specific titles of those personnelfulfilling the responsibilities of the positions delineated in these Technical Specifications, shall be documented in the UFSAR.

b. The plant manager shall be responsible for overall safe operation of the ptan{ggllift and shall have control over those onsite activities necessary for safe of the plan+ryglear-lrJel.

c.

A specified corporate otficer shal! have corporate responsibility for everall and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technicalsupport to the pln{agifiy to ensure

d. The individuals who train the carry out health physics, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sutficient organizational freedom to ensure their independenee frem uni+Eacilitv Staff The unitfagry staff organization shall include the following:

is at teast one snitt ma Noru-Cenlrteo ope ETIELTIANDI.EB:

Davis-Besse a.

5.2-1 Amendment 274 l

Organization 5.2

b. Shift crew composition may be less than the minimum requirement of 10 CFR 50,54(mX2Xi) and SpecificationsS.2.2.aand+2+lfor a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirementsf@

theloiloudnsiondilion$re-mel

1) No nuclear fuel m Zl tlo movement ot to S) No unmanned shift Oue to an incomlno orabsent:

Davis-Besse 5.2-1 Amendmenl2Tg I

Organization 5.2 5.2 Organization 5.2.2 tlnitFacilitv Staff (continued)

A radiation protection technician shall be on site over the nuclear fud. The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position; (ruoru-cenlHeo op oresent in tne cont pool; tne s[6llM

@be a CERTIFIED FUEL HANDLERJ-he+ssistant

and When the reaeter is eperating in MODE 1; 2; 3; er 4 an individual shall previae advisery t snat Ue orovUea U c.

d e

f Davis-Besse 5.2-2 Amendment 289