ML20057B477

Summary of 930824 Meeting W/Util Re Implementation of dual-site Senior Reactor Limited to Fuel Handling (Lsr) Program.List of Meeting Attendees & Meeting Handouts Encl

ML20057B477
Person / Time
Site:	Peach Bottom, Limerick
Issue date:	09/15/1993
From:	James Shea Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9309220103
Download: ML20057B477 (18)

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i 1* E UNITED STATES l'  ! NUCLEAR REGULATORY COMMISSION v W ASHINGTON, D.C. 2055%0001 4

September 15, 199 Docket Nos. 50-277/50-278 and 50-352/50-353 i i

4 LICENSEE: Philadelphia Electric Company, et al.

FALLITY: Peach Bottom Atomic Power Station, Units 2 and 3, and i

Limerick Generating Station, Units 1 and 2

SUBJECT:

REQUALIFICATION AND REACTIVATION PROGRAMS FOR SENIOR REACTOR OPERATORS LIMITED TO FUEL HANDLING J C

On August 24, 1993, the NRC staff met with representatives of the Philadelphia

~ Electric Company (PEco) to discuss implementation of the dual-site, senior  ;

reactor operator limited to fuel handling (LSR0) program. The meeting was  !

requested by PEco to discuss certain issues raised by the NRC staff described

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in Inspection Report 50-277/93-15 and 50-278/93-15. A list of attendees is i included as Enclosure 1. '

The meeting opened with a brief presentation by PECo on the history of the dual-site LSR0 program at Peach Bottom and Limerick. PEco requested in June )

1990 to implement a program to license a limited number of LSR0s to supervise i refueling floor activities at both Peach Bottom and Limerick. The staff approved the plan in October 1990. The first group of PECo LSR0s were l licensed at Limerick in September 1990 and at Peach Bottom in January 1991. {

The staff and PEco met in May 1991 to discuss various aspects of the requalification portion of the new dual-site LSR0 program. On May 31, 1991, PEco requested an exemption from the requirements of 10 CFR 55.53(e), which states that, in order to maintain an active status, the licensee (in this case, the LSR0) shall actively perform the functions of an operator or senior operator on a minimum of seven 8-hour shifts or five 12-hour shifts per calendar quarter. In the exemption renuest, PECo proposed that LSR0s maintain an active status by performing the functions of an operator for 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> semiannually. In justifying the request, PECo stated that, with the expected schedule of refueling outages for the four PEco units, the LSR0s would not be able to meet the existing requirements of 10 CFR 55.53(e).

The staff responded to the exemption request by letter dated September 27, 1991. In that letter, the staff stated that the exemption request was not necessary. The existing regulations, specifically 10 CFR 55.53(f)(2), ,

contains provisions for reactivating a license that has not been maintained in  !

an active status. The regulation includes a requirement that the licensee (the LSR0) seeking to be reactivated complete, as a minimum, one shift of shift functions under the direction of a senior operator and in the position j to which the individual will be assigned. In the September 27, 1991 letter, tne -taff described some of the functions that should be performed during that '

reactivation shift. }

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l PEco discussed the results of the LSR0 program since its inception. The licensee stated that the quality.of fuel handling activities is significantly l improved with fewer fuel movement errors and more efficient' operations. The '

staff concurred that, with the exception of some early program startup problems, the LSR0 program has been an improvement to PEco's refueling activities.

l The licensee outlined their LSR0 requalification program. LSR0s complete 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of requalification training just prior to each scheduled refueling outage. Under the present schedule of one refueling outage per year at each  ;

site, the LSR0s undergo 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> per year of requalification training. The training topics include a selection of topics from the initial qualification training program as well as discussions on scheduled plant modifications and I outage workscope. The LSR0s undergo a yearly requalification exam. The location of the exam alternates between the Limerick and Peach Bottom sites on ,

a yearly basis.  !

l In addition to the requalification training, the LSR0s undergo 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of reactivation proficiency watchstanding activities. The scope of activities performed during the proficiency watch is described by the licens2e in a  !

proposed revision to procedure LSR0-0000, Revision 2, " Multi-Site Senior j Reactor Operator Limited to Fuel Handling (LSR0) Program Plan" Unclosure 2). >

According to the draft procedure, the reactivation shift must cecur no earlier than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the scheduled start of core alterations. The procedure  ;

contains minimum activities needed for reactivation including: 1) a tour of -

the Main Control Room to become familiar with equipment statr,s and  !

watchstanding; 2) attendance at an operations shift turr.:rier meeting; 3) tour of the refuel floor for the unit in which the core alterations are to be  !

performed; and 4) a review of the applicable unit Limiting Condition for  !

Operation (LCO) log. The procedure also allowed'other activities to be  !

creditable toward the reactivation time requirements including, but not '

limited to: 1) handling of fuel in the fuel pool or vessel, 2) certain in-vessel maintenance work, 3) performance of refueling platform surveillance -

tests, and 4) performance of procedures to establish conditions and verify prerequisites for starting core alterations.

The staff noted that the licensee has conducted these reactivation tasks under the dire.ction of active SR0s in the past, as required by 10 CFR Part 55, and commented that the training procedure should explicitly capture this requirement. The staff expressed concern that certain in-vessel maintenance tasks might fall outside the scope of activities requiring a license, and thus should not be credited toward the reactivation requirements. The licensee committed to specifying in the procedure which in-vessel maintenance activities could be credited toward reactivation. Finally, the staff noted that the procedure revisions contained an explicit requirement that the reactivation shift activities occur within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the planned start of core alterations. The staff viewed this as a positive control on the proximity of the reactivation training to performance of the licensed functions.

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The staff concluded by stating that the overall performance of the LSR0 program was good and that requalification and reactivation activities met the .

requirements of 10 CFR Part 55. The staff did note that the previous lack of -

documentation of reactivation program requirements represented a weakness. The staff also noted that the proposed procedu e revision presented by the licensee adequately addressed that weakn ..

k Joseph . Shea, Project Manager )

Project Directorate I-2  :

Division of Reactor Projects - I/II 1 Office of. Nuclear Reactor Regulation  !

Enclosures:

1. List of Meeting Attendees j

2. Licensee LSR0 Program Plan I

cc w/ enclosures:

Licensee and Service List -

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t Mr. George A. Hunger, Jr. Peach Bottom Atomic Power Station, Philadelphia Electric Company Units 2 and 3 Limerick Generating Station, ,

Units 1 and 2  ;

cc.

J. W. Durham, Sr., Esquire Mr. William P. Dornsife, Director i Sr. V.P. & General Counsel Bureau of Radiation Protection l Philadelphia Electric Company Pennsylvania Department of 2301 Market Street, S26-1 Environmental Resources  !

Philadelphia, Pennsylvania 19101 P.O. Box 8469 Harrisburg, Pennsylvania 17105-8469  !

Philadelphia Electric Company ATTN: Mr. D. B. Miller, Vice President Board of Supervisors  ;

Peach Bottom Atomic Fmwer Station Peach Bottom Township l Route 1, Box 208 R. D. #1 Delta, Pennsyh>:nia ' 17314 Delta, Pennsylvania 17314 i Philadelrhia Electric Company Public Service Comission of Maryland I ATTN: Regulatory Engineer, Al-2S Engineering Division l Peach Bettom Atomic Power Station /TTF . Chief Engineer l Route 1, Box 208 l E. Baltimore Street Delta, Pennsylvania 17314 Baltimore, MD 21202-3486 i Resident Inspector Mr. Richard McLean U.S. Nuclear Regulatory Commission Power Plant and Environmental )

Peach Bottom Atomic Power Station Review Division P.O. Box 399 Department of Natural Resources Delta, Pennsylvania 17314 B-3, Tawes State Office Building Annapolis, Maryland 21401 Regional Administrator, Region U.S. Nuclear Regulatory Commission Mr. Rod Krich, 52A-5 475 Allendale Road Philadelphia Electric Company King of Prussia, Pennsylvania 19406 955 Chesterbrook Boulevard Wayne, Pennsylvania 19087-5691 Mr. Roland Fletcher Department of Environment Mr. David R. Helwig, Vice President 201 West Preston Street Limerick Generating Station Baltimore, Maryland 21201 P.O. Box A Sanatoga, Pennsylvania 19464 Carl D. Schaefer External Operations - Nuclear Mr. Robert Boyce Delmarva Power & Light Company Plant Manager P.O. Box 231 Limerick Generating Station l Wilmington, DE 19899 P.O. Box A j Sanatoga, Pennsylvania 19464 I

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i Mr. George A. Hunger, Jr. Peach Bottom Atomic Power Station, ,

Philadelphia Electric Company Units 2 and 3 i Limerick Generating Station,  !

Units 1 and 2 l

Mr. Craig L. Adams Mr. Neil S. Perry i Superintendent - Services Senior Resident Inspector  ;

Limerick Generating Station U.S. Nuclear Regulatory Commission  ;

, P. O. Box A - P.O. Box 596 i Sanatoga, Pennsylvania 19464 Pottstown, PA 19464 i i

Mr. James L. Kantner Library l l Regulatory Engineer U.S. Nuclear Regulatory Commission l Limerick Generating Station Region I  !

P. O. Box A .

475 Allendale Road ,

Sanatoga, Pennsylvania 19464 King of Prussia, PA 19406-  !

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Mr. Larry Hopkins Mr. John Doering, Chairman  ;

Superintendent-Operations Nuclear Review Board '

l Limerick Generating Station Philadelphia Electric Company j i P. O. Box A 955 Chesterbrook Boulevard  ;

Sanatoga, Pennsylvania 19464 Mail Code 52C-1  :

Mr. James A. Muntz  !

Superintendent - Technical i

Limerick Generating Station l' P.O. Box A Sanatoga, Pennsylvania 19464 i t

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ENCLOSURE 1 MEETING BETWEEN NRC AND PHILADELPHIA ELECTRIC COMPANY ON REOUALIFICATION AND REACTIVATION OF LIMITED SENIOR REACTOR OPERATOR LICENSES  ;

Auaust 24. 1993 l

l NAME ORGANIZATION R. Krich PECo l P. Berry. PEco 1 G. Stewart PEco i R. King PEco K. Borton )

PEco j M. Boyle NRC/NRR/PDI-2 R. Gallo NRC/NRR/HOLB L. Bettenhausen NRC/RGN-I/03~

B. Norris _NRC/RGN-I/PBAPS W. Swenson NRC/NRR/HOLB  !

D. Lange NRC/NRR/HHFB J. Lennartz NRC/NRR/HOLB  :

R. Pelton NRC/NRR/HHFB J. Shea NRC/NRR/PDI-2 S. Maingi Commonwealth of Pennsylvania j

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ENCLOSURE 2 LSRO-0000, Rav 002 >

Page 1 of 11 PHILADELPHIA ELECTRIC COMPANY  ?

NUCLEAR TRAINING DIVISION MULTI-SITE SENIOR REACTOR OPERATOR LIMITED TO FUEL HANDLING (LSRO)

PROGRAM PLAN l

1.0 PURPOSE 1.1 The purpose of the Multi-Site Senior Reactor Operator Limited to Fuel Handling (LSRO) Program Plan is to describe the program administration and course-implementation of the LSRO Training Program.  ;

2.0 SCOPE 2.1 This program plan identifies training requirements for initial licensing of an LSRO candidate as set forth in NRC Examiner Standard ES-701 (Reference 3.2). Training implementation is detailed in LSRO-0001, " Multi-Site  ;

Senior Reactor Operator Limited to Fuel Handling (LSRO)

Initial Training Course Plan". i l

2.2 This program plan also identifies requalification  !

training requirements to maintain an LSRO license as set l forth in NRC Examiner Standard ES-702 (Reference 3.2). '

Training implementation is detailed in LSRO-0002, " Multi-Site Senior Reactor Operator Limited to Fuel Handling (LSRO) Requalification Training Course Plan".

3.0 REFERENCES

.. I 3.1 10 CFR 55, " Conditions for Licenses" 3.2 NUREG 1021, " Operator Licensing Examiner Standards" 3.3 NUREG 1123, " Knowledge and Abilities Catalog for Nuclear Plant Operators: Boiling Water Reactors" 3.4 NUREG/BR-0122, " Examiner's Handbook for Developing Operator Licensing Examinations" l

3.5 INPO ACAD 91-012, " Guidelines for Training and Qualification of Licensed Operators" 3.6 INPO ACAD 91-015, "The Objectives and Criteria for Accreditation of Training in the Nuclear Power Industry" 1

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1 3.7 INPO ACAD 91-016, "The Process for Accreditation of i Training in the Nuclear Power Industry" )

3.8 Peach Bottom Technical-Specifications 3.9 Limerick Technical Specifications 3.10 Peach Bottom UFSAR Volume 5, Section 13.3 3.11 Limerick UFSAR Volume 18, Section 13.2 3.12 Peach Bottom Operations Manual 3.13 Limerick Procedure A-7, " Shift Operations" l

3.14 Common Nuclear Procedures TQ-C-1 through TQ-C-9 l 4

i 3.15 Limited Senior Reactor Operator Interface Committee Charter, Effective Date June 9, 1991.

3.16 D. M. Smith letter dated June 3, 1991, " Limited SRO Program" 3.17 Position Guide, " Tech Staff LSLO" dated 09/90

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3.18 NTD Department Unique Guidelines for Operations Training l l 3.19 NRC Letter from R. J. Clark to G. J. Beck (PECo) dated l September 29, 1991 - PECo Document Control' Desk Number l CCN 91-00987 e l

l 3.20 Medical Instruction MDI/N-2; " Procedure for the Medical l Evaluation of personnel requiring ' Nuclear Power Plant--

l Operating Licenses" 4.0 DEFINITIONS 4.1 SENIOR REACTOR OPERATOR, LIMITED TO FUEL HANDLING (LSRO):

An individual holding a license issued by the Nuclear Regulatory Commission to direct the fuel handling activities of operators and to manipulate fuel handling controls. Tnese individuals are licensed and authorized to supervise the performance of core alterations as defined in Peach. Bottom and Limerick Technical Specifications. LSRO's are also qualified and authorized to supervise invessel maintenance activities and special nuclear material moves on the refuel floors which are not considered to be core alterations.

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m LSRO-0000, Rev 002

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Page 3 of 11 5.0 RESPONSIBILITY 5.1 DIRECTOR - NUCLEAR TRAINING DIVISION (NTD) 5.1.1 Responsible for the overall coordination and conduct of LSRO training activities. This includes responsibility for coordination of training commitments to external organizations, accreditation support, determining course content, directing course preparations and development and approval of course training materials. The Director NTD is jointly responsible with the site Directors - Training for coordination of financial and personnel _esources associated with LSRO Initial and Rerpaalification Training.

5.1.2 Approve the LSRO Program / Course Plans.

5.1.3 Designate a Instructor - LSRO for each LSRO Initial and Requalification Training course.

5.1.4 Jointly responsible with the Manager - Reactor Services Section (NMD) for evaluation of deficient LSRO trainee exam results and determination as to whether an LERO trainee should remain in a training status.

5.2 DIRECTOR - TRAINING (PBAPS, LGS) 5.2.1 Ensure implementation of their respective site specific LSRO Initial and Requalification Training courses.

5.2.2 Approve the LSRO Program / Course Plans.

5.2.3 Provide classrooms, instructor space, and clerical support during implementation of LSRO Initial and Requalification Training at the respective host site.

5.2.4 Ensure that the site Nuclear Training Section is represented at the interface meeting held prior to each refueling outage.

5.2.5 Jointly responsible with the Manager - Reactor Services Section (NMD) for evaluation of deficient LSROR trainee exam results and determination of remedial training in accordance with current LOR training guidance at the respective exam site.

LSRO-0000, Rav 002

.Page 4 of 11 5.3 SENIOR MANAGER - OPERATIONS (PBAPS, LGS) 5.3.1 Approve the LSRO Program / Course Plans.

l 5.3.2 Approve the content of the site specific LSRO Initial and Requalification Training- course material or designating, through the Manager- -

Operations Training (PBAPS, LGS), the applicable Plant Staff /SME.

5.3.3 Ensure an Oral Certification Board is convened in.

accordance with current training procedures (LGS only).

5.3.4 Ensure that the Operations Group is represented at the interiace meeting held prior to each refueling j outage and that applicable operations related topics are included in LSRO Requalification Training.

I 5.4 MANAGER - REACTOR SERVICES SECTION (NMD) 5.4.1 Ensure LSRO(R) trainees meet course prerequisites as stated in section 6.0. I 5.4.2 Approve the LSRO Program / Course Plans. l 5.4.3 Approving the content of the - LSRO Initial and Requalification Training course material or i designating, through the Manager - Nuclear Support (NTD), the applicable NMD Staff /SME.

5.4.4 Jointly responsible with the Director - - Nuclear Training Division (NTD) for evaluation of deficient LSRO trainee exam results and determination as to whether an LSRO trainee should remain in a training status. ,

5.4.5 Jointly responsible with the Director - Training (Exam Site) for evaluation of deficient LSROR trainee exam results and determination of remedial training in accordance with current LOR training guidance at the respective exam site, 5.4.6 Sponsor an interface meeting prior to the scheduled start of each refueling outage to determine the content of LSRO Requalification Training (Reference l 3.15).

5.4.7 Interface with the Employing Officers of LSRO's not permanently assigned to the Reactor Services l Section on all matters regarding the training and l use of these individuals.

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LSRO-0000, Rav 002 i Page 5 of 11 i 5.5 LSRO EMPLOYING OFFICERS 5.5.1 Make LSRO trainees available for LSRO Initial and i Requalification Training as directed by the Nuclear Group Vice Presidents and in accordance with the ,

Limited SRO Program (Reference 3.17).  !

5.6 MANAGER - OPERATIONS TRAINING (PBAPS, LGS) 5.6.1 Monitor course administration and implementation.

5.6.2 Identify applicable Plant Sta*f/SME for approving LSRO Initial and Requalificat.;an Training course materials.

5.6.3 Approve for use LSRO Initial and Requalification Training course materials.

5.7 MANAGER - NUCLEAR SUPPORT (NTD) 5.7.1 Supervise course administration and inplementation.

5.7.2 Approve for use LSRO Initial and Requalification Training course materials. )

5.7.3 Recommend an LSRO trainee for evalua tion to the Director - Nuclear Training Division (.ITD) and the Manager - Reactor Services Section (:IMD) due to deficient exam results.

l S.8 LEAD INSTRUCTOR - LSRO 5.8.1 Individual designated by the Director -

NTD, to coordinate all training activities associated with 1 a particular LSRO Initial or Requalification l Training Course.

5.8.2 Maintenance of all L5'R O Initial and Requalification l Training course materials. l 5.8.3 Tracking and assessing LSRO(R) trainee performance during LSRO Initial and Requalification Training. l 5.8.4 Recommend a LSRO(R) trainee evaluation be conducted to the Manager - Nuclear Support (NTD).

5.8.5 Provide interface and coordination between LSRO(R)

Trainees, LSRO(R) Instructors, NTD, NMD, NESD-Licensing, LGS - NTS, LGS Operations, PBAPS - NTS, PBAPS Operations as required for LSRO Initial and Requalification Training course implementation.

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LSRO-0000, Rsv 002 Page 6 of 11 l 5.8.5 Act as a single point of contact to internal and external agencies regarding LSRO Initial and Requalification Training and the licensing process.

l 5.8.6 Ensure equipment availability to support LSRO j training and evaluation.

l 1 l 5.8.7 Interface with plant work groups to minimize l interference with LSRO training and evaluation.

5.9 LSRO TRAINEES / CANDIDATES 5.9.1 LSRO trainees / candidates are responsible to comply with current training procedures (Reference 3.14).

6.0 PREREOUISITES I

6.1 Prerequisites are identified in NUREG 1021 and the  !

applicable LSRO course plan. Prerequisites addressed are:

Experience Requirements i Educational Requirements 1 Medical Requirements l Access Requirements j 6.2 TARGET POPULATION 6.2.1 LSRO trainees are selected from Peach Bottom Atomic Power Station, Limerick Generating Station, and the Station Support Department.

I 7.0 PROCEDURE l 7.1 LSRO CANDIDATE SELECTION l .-

l 7.1.1 The Superintendent, Reactor Services Section, will l sponsor and conduct the selection of a sufficient j number of candidates to support the conduct of j scheduled LSRO Initial Training courses.

l 7.2 LSRO INITIAL AND REQUALIFICATION TRAINING l

l 7.2.1 Training implementation for LSRO Initial Training l is detailed in LSRO-0001; " Multi-Site Senior l Reactor Operator Limited to Fuel Handling (LSRO) l Initial Training Course Plan".

I l 7.2.2 Training implementation for LSRO Requalification l Training is detailed in LSRO-0002; " Multi-Site l Senior Reactor Operator Limited to Fuel Handling '

j (LSRO) Requalification Training Course Plan".

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i LSRO-0000, Rav 002 Pcge 7 of 11 l 7.3 LSRO INTERFACE MEETINGS l l l 7.3.1 An interface meeting will be conducted a minimum of l sixty days prior to the scheduled start of each j refueling outage to identify and address issues j related to the training and use of LSRO's in the l l upcoming outage. This meeting will be scheduled l and conducted by the Manager, Reactor Services l Section, or his designated representative.

j Cognizant representatives from NMD, NTD, and both l site's Operations, Training, and Licensing sections j should be present. i l

l 7.4 LSRO LICENSE ACTIVATION l

l 7.4.1 The Manager, Reactor Services Section, will l maintain documentation of the time that LSRO's are j actively engaged in performing license related I j duties in order to prove satisfaction of the j license activation requirements of reference 3.1.

l Documentation shall be recorded on Exhibit 9.1 or  !

l equivalent.

l l 7.4.2 Time spent supervising or performing the following l activities may be counted towards satisfying the l license activation requirements of reference 3.1:

I l 7.4.2.1 Handling of new or irradiated fuel in the reactor j vessel or fuel pool.

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l 7.4.2.2 Invessel maintenance activities requiring Ehe use j of the refueling platform main or auxiliary hoists, j regardless of whether there is fuel in the core j during these activities.

l l 7.4.2.3 Performance of refueling platform Surveillance l Tests or Maintenance , procedures for checkout of the j refueling platform over the core.

l l 7.4.2.4 Normal FHD shift turnover activities, including j attendance at the Operations shif t turnover meeting l in the main control room.

l l 7.4.3 Time spent supervising or performing the activities j listed in 7.4.2 at Peach Bottom Atomic Power l Station and Limerick Generating Station may be j counted cumulatively toward meeting the license l activation requirements of reference 3.1.

l Satisf action of these requirements using cumulative l time at one or both stations will maintain active l license status at both stations.

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N LSRO-0000, Rsv 002 Page 8 of 11 l 7.4.4 Prior to participation in any refueling outage, j active LSRO's must complete the following tasks

' prior to performing or supervising CORE ALTERATIONS. These tasks shall be performed no

, earlier than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the scheduled start j of CORE ALTERATIONS:

l l 7.4.4.1 A tour of .the Main Control Room with particular l attention to equipment and systems status for the j unit in which CORE ALTERATIONS are to be performed.

l l 7.4.4.2 Attendance at an Operations shift turnover meeting j in the Main Control Room.

l l 7.4.4.3 A tour of the refuel floor of the~ unit in which l CORE ALTERATIONS are to be performed.

l l 7.4.4.4 A review of the applicable unit LCO Log.

l l' 7.4.5 LSRO's unab'te to maintain their license active per reference 3,1 shall, prior to performing licensed duties, reactivate their license in accordance with

, sections 7.4.6 and 7.4.7 of this program plan.

l License reactivation at Peach Bottom or Limerick Stations fully reactivates the dual-site license,

[ and shall be documented on Exhibit 9.2 or 1

equivalent.

i 7.4.6 The primary purpose of a license reactivation shift li is to ensure that the LSRO is fully familiar with y plant conditions, ongoing evolutions, and j Operations shift team routines prior to j participating in CORE ALTERATIONS. A. license j reactivation shift, as required by reference 3.1 l and described by reference 3.19, must include the l following activities under the observation of an j active SRO or LSRO, and must occur no earlier than j 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the scheduled start of CORE l ALTERATIONS:

l l 7.4.6.1 A tour of the Main Control Room with particular j attention to equipment and systems status for the j unit in which CORE ALTERATIONS are to be performed.

i l 7.4.6.2 Attendance at an Operations shift turnover meeting j in the Main Control Room.

l l 7.4.6.3 A tour of the refuel floor of the unit in which l CORE ALTERATIONS are to be performed.

l l 7.4.6.4 A review of the applicable unit LCO Log.

e LSRO-0000, R v 002 P;ga 9 of 11 l 7.4.7 The following activities may also be performed in j addition to those specified in 7.4.6 to complete a j license reactivation shif t, as plant conditions and j activity schedule allow:

i l 7.4.7.1 Handling of new or irradiated fuel in the reactor j vessel or fuel pool (this may be done at any time l during the quarter for which reactivation is l required, as long as it is done in the company of l an active LSRO or SRO).

l 7.4.7.2 Invessel maintenance activities requiring the use l of the refueling platform main or auxiliary hoists, l regardless of whether there is fuel in the core l during these activities.

l 7.4.7.3 Performance of refueling platform Surveillance l Tests or Maintenance procedures for checkout of the j refueling platform over the cere.

l l 7.4.7.4 Normal FHD shift turnover activities, including l attendance at an Operations shift turnover meeting l in the Main Control Room.

l l 7.4.7.5 Performance of procedures used to establish l conditions and verify prerequisites for starting l CORE ALTERATIONS.

l 7.4.7.6 Observation of Main Control Room activities during l preparations for performing CORE ALTERATIONS. l l 7.5 MEDICAL EXAMINATIONS l l

l 7.5.1 LSRO medical examinations shall be conducted in j accordance with reference 3.20.

8.0 DOCUMENTATION 8.1 Course documentation will be maintained in accordance with applicable LSRO Initial and Requalification Training course plans.

9.0 EXHIBITS l 9.1 LSRO License Active Status Verification Sheet l 9.2 LSRO License Reactivation Documentation Sheet

c LSRO-0000, Rsv 002

. P gn 10 of 11 LSRO LICENSE ACTIVE STATUS VERIFICATION SHEET l

l Licensee: Term:

l License is ACTIVE / INACTIVE at beginning of this term:

l Manager - Reactor Services  !

NOTE: If license is INACTIVE at beginning of term, no logging l of activities may be performed until reactivation is l l

complete. l PRIOR TO PERFORMING CORE ALTERATIONS: l l

Requalification Training Status Current: 1 LEAD INSTRUCTOR - LSRO l

Section 7.4.4 activities complete: / /

LOCATION DATE TIME No. Hours

• Activity (from section 7.4.2) l l

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TOTAL i AT END OF TERM:

If licensee does not meet or exceed the minimum number of hours required to maintain active status, Verification Sheet for next term shall indicate the license is inactive.

If licensee meets or exceeds the minimum number of hours required to maintain active status, Verification Sheet for next term shall indicate the license is active.

Verified:

Manager - Reactor Services Exhibit 9.1 Page 1 of 1

LSRO-0000, Rav 002 g)

. Paga 11 of 11 LSRO LICENSE REACTIVATION DOCUMENTATION SWEET Licensee: Term:

REOUALIFICATION TRAINING STATUS CURRENT:

LEAD INSTRUCTOR - LSRO REACTIVATION SHIFT To activate an inactive license, the licensee must ensure

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compliance with the following c~riteria:

1. The licensee has completed a minimum of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of shift functions under the direction of an active senior licensed operator (SRO/LSRO). The 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> must have {

included: '

a. A tour of the Main Control Room with particular attention to equipment and systems status for. the _

unit in which CORE ALTERATIONS are to be performed. '

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b. Attendance at an Operations shift turnover meeting  !

in the Main Control Room. 1 l c. A tour of the refuel floor of the unit in which_

CORE ALTERATIONS are to be performed.

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d. A review of the applicable unit LCO Log.

2. Additional activities which may'be used to complete the shift are described in section 7.4.7. i

3. A log entry must be made in the Shift Manager's Log to document the fact that the licensee was present on shif t under instruction.

[ ATE / SHIFT # HOURS SRO/LSRO INIT ACTIVITY PERFORMED / OBSERVED l

l Reactivation Location: Unit:

Verified:

l Manager - Reactor Services Forward completed form to the Manager - Support Branch, NTD l

Exhibit 9.2 I Page 1 of 1 i

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The staff ncluded by stating that the overall performance of the LSR0 program  :,)od and that requalification and reactivation activities met the i requirem-n 'f 10 CFR Part 55. The staff did note that the previous lack of t document . > of reactivation program requirements represented a weakness. The t staff also noted that the proposed procedure revision presented by the licensee adequately addressed that weakness.

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/S/

Joseph W. Shea, Project Manager.

Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation 3

Enclosures:

I. List of Meeting Attendees .

2. . Licensee LSR0 Program Plan cc w/ enclosures:

Licensee and Service List  ;

DISTRIBUTION w/ Enclosure 1 DISTRIBUTION w/ Enclosures 1 and 2  ;

TMurley/FMiraglia iDocket File = '

JPartlow NRC & Local PDRs  ;

SVarga/JCalvo PDI-2 Reading MBoyle JShea M0'Brien FRinaldi -

OGC EWenzinger, RGN-I l' EJordan CAnderson, RGN-1 WDean BNorris, RGN-I  !

RPelton i WSwenson DLange JLennartz RGallo  :

LBettenhausen  :

ACRS(10)

VMcCree, ED0 0FFICE PD17MOA3 hl)22PM PDI-2/DVM6Lh[RGN-I/ bks /0B PDI-2/D; p NAME MhkrbkM FRinNi kbilo /ABetNM en MBoyl b /

DATE h/f/93 6[0//93 1/I/93 /lh/93 4 /lo/93 7 / 16

/93 0FFICIAL VCORD COPY DOCUMENT NAME: PB8-29.MTS

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