ML20236H447

Informs That Attachments to 980529 Response to NRC 980518 RAI Re Application for Review & Approval of site-specific License for ISFSI at NAPS May Be Placed in PDR

ML20236H447
Person / Time
Site:	North Anna
Issue date:	06/30/1998
From:	Ohanlon J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Paperiello C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML20236H449	List: ML20236H447 ML20236H508 ML20236H531 ML20236H539 ML20236H554 ML20236H556 ML20236H563 ML20236H570
References
RTR-NUREG-0612, RTR-NUREG-612 98-328A, TAC-L22113, NUDOCS 9807070213
Download: ML20236H447 (5)

Text

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Waisir EuccTRIC AND POWER CONWANY RscusmNo, VHMilNI A 23261 l

June 30, 1998 l

Mr. Carl J. Paperiento, Director Serial No. 98-328A Office of Nuclear Material Safety and Safeguards NL&OS/MAE R0

( U. S. Nuclear Regulatory Commission Docket No. 72-16 l Washington, D. C. 20555 l l Gentlemen:

! 1 l VIRGINIA ELECTRIC AND POWER COMPANY l

NORTH ANNA INDEPENDENT SPENT FUEL STORAGE INSTALLATION l TRAINING DOCUMENTATION (TAC NO. L22113) 4 Virginia Electric and Power Company (Virginia Power) submitted an application for the review and approval of a site-specific license for an independent cpent fuel storage installation (ISFSI) at North Anna Power Station on May 9,1995 (Serial No.95-195).

i The NRC requested additional information to support the application on May 18,1998.

l Virginia Power provided the requested information in a letter dated May 29,1998 (Serial No.98-328). The attachments to our May 29,1998 letter (Serial No.98-328) j may be placed in the Public Document Room.

! Please contact us if you have any questions or require additional information. '

Very truly yours, t

kr Fo rt.,

James P. O'Hanlon l' Senior Vice President - Nuclear Commitments made by this letter: None cc: Mr. J. W. Shea Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission, Mail Stop 14-H-22 i

! Washington, D. C. 20555 l

l United States Nuclear Regulatory Commission l

Attention: Document Control Desk Washington, D. C. 20555-0001 Mr. M. J. Morgan NRC Senior Resident inspector North Anna Power Station 9007070213 990630 PDR ADOCK O

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ATTACHMENT 1 Response To A Request For Additional Information 4 l 1.0 NRC REQUEST in a letter dated April 23,1998, Virginia Power committed to constructing a crane enclosure to prevent the weather-driven spread of contamination from use of the cask lifting equipment outside the Decontamination Building. Until the crane enclosure is l constructed, Virginia Power committed to limit the movement of those casks ready for l transport to times when weather, including precipitation and wind, will not be a factor in i the spread of contamination. Because Virginia Power did not commit to a specific time frame for constructing the crane enclosure, the staff must evaluate the proposed interim '

alternatives as permanent measures.

Provide additional detail regarding the measures that will be taken to ensure that contamination does not and has not spread beyond the Decontamination Building as a ,

result of using potentially contaminated equipment, such as crane cables. Such detail '

may include the previouc!y committed procedure restrictions on weather but should also l reflect good health physics practices as determined by Virginia Power. For example, it may also include use of temporary barriers (protecting either the general area or ,

specific points of concern such as yard drains) and additional contamination surveys of l- the environs after cask handling activities are completed. I 1.1 VIRGINIA POWER RESPONSE l

Virginia Power currently plans to design and construct a crane enclosure by December 31,1999, to prevent the weather-driven spread of contamination from use of the cask lifting equipment outside the Decontamination Building. Good health physics practices will be used to ensure there is no spread of contamination to outside areas.

Radiological control procedures have been developed to address the cask handling activities and contain controls to prevent the spread of contamination during cask L handling activities. Consistent with our current radiological control program, the following controls will be used to reduce the potential for contamination in the yard area during cask handling activities:

• The cask, crane hook, and lift beam must be decontaminated to less than 1000 dpm/100cm2 before moving from the Decontamination Building.

• The crane cables will also be decontaminated to the maximum extent possible.

. Follow-up surveys of the yard will be performed after the crane is placed back in the Decontamination Building.

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Until the crane enclosure is completed, an additional precaution is being included in l Operating Procedure 0-OP-4.35, TN-32, Cask Loading and Handling, to further prevent the weather-driven spread of contamination. This precaution prevents the cask crane from being moved to the yard area if there is any form of precipitation anticipated during the evolution or if there are wind conditions anticipated that would adversely affect the spread of contamination.

2.0 NRC REQUEST Provide copies of %r administrative procedures that demonstrate compliance with 10

, CFR Part 72, Subpart I. Specifically, provide the procedures which address (1) l program administration, (2) requirements for personnel training by position, (3) certification requirements and (4) instructor qualification requirements. In addition, provide the administrative procedures which demonstrate compliance with 10 CFR 72.194.

2.1 VIRGINIA POWER RESPONSE Virginia Power has developed a draft program that will meet the requirements of 10 l CFR Part 72, Subpart 1. A program guide is being established to document the qualification requirements of personnel assigned to perform spent fuel dry cask storage duties. These duties include cask crane operation, transporting, testing, and loading of nuclear fuel associated with spent fuel dry cask storage. Qualification packages will consist'of a qualification card, job performance measures, and a productive work evaluation record. Operations Department management selects trainees for this program. Training on spent fuel dry cask storage is completed after personnel have completed the Fuel Handling Program, in addition, a Spent Fuel Dry Storage Cask System training module is being' developed.

This training module will provide a general and detailed description of the Spent Fuel Dry Storage Cask System. Information related to the spent fuel storage cask design criteria, basic cask operations, transporter operations, and an overview of the Independent Spent Fuel Storage Installation (ISFSI) facility design and Safety Analysis Report are contained in the training module. This training module is being incorporated into the Nuclear Control Room Operator Development Program. Lesson plans are also being developed to assist training instructors in conveying pertinent information related to the Spent Fuel Dry Storage Cask System and the ISFSI.

Several job performance measures (JPMs) are being developed to ensure trainees understand the operation of the Spent Fuel Dry Cask Storage System. Some of the JPMs include operation of the spent fuel cask crane, transport of the dry storage cask Page 2 of 4

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l in the Decontamination Building and Fuel Building, loading of the cask, assembly of the cask, leak testing the cask, transfer of the cask to the yard area, and operation of the transporter.

l Copies of the draft program guide, training module, lesson plans, and JPMs are l attached for your information. Approval of and training on these documents will be performed to support the ISFSI license schedule.

In our response to the request for additional information dated May 28,1998 (Serial No. ,

98-274A), we indicated that the 125-ton cask handling crane and 10-ton auxiliary crane  !

would be included in the NUREG-0612 heavy loads program by July 1,1998. Virginia l Power Administrative Procedure (VPAP) 0809, NUREG-0612 Heavy Load Program, provides requirements to ensure that the movement of heavy loads are adequately controlled. VPAP-0809 specifies those personnel operating overhead handling systems will be trained and qualified to perform heavy load lifts.  !

l The qualification requirements for the crane operators are delineated in VPAP-0810, I Crane and Hoist Program. VPAP-0810 specifies the knowledge, practical, and requalification testing requirements for crane operators. VPAP-0810 also specifies that crane operators will meet the applicable ANSI standard for physical requirements for the crane being operated. The station nurse verifies that Virginia Power crane operators meet the physical requirements of the applicable ANSI standard. The Training Department maintains the list of qualified crane operators based on successful completion of applicable knowledge testing, practical testing and physical requirements testing. Personnel that do not meet applicable testing requirements are removed from the list of qualified crane operators until they become requalified. Copies of VPAP-0809 and VPAP-0810 are attached for your information.

l The North Anna Instructor Training Program is based upon INPO's Guidelines for instructor Training and Qualification (INPO 88-012), the American National Standards institute's Selection and Training of Nuclear Power Plant Personnel (ANSI 18.1,1971),

and Standards for Qualification and Training of Personnel for Nuclear Power plants (ANSI 3.1, Draft 1979). These instructional and technical requirements are implemented by TRCP-0009, instructional Staff Training and Qualifications. A copy of TRCP-0009 is attached for your information.

The Nuclear Instructor Training and Certification Program (NITCP) is a performance-based program which requires the instructor to demonstrate instructional skills in the actual training environment. Instructors are qualified on the 29 tasks selected for the NITCP program. The program consists of three phases: a Basic Training Program designed for new instructors, an Advanced Training Program consisting of five guided self-study units, and a Continuing Training Program.

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l-l Operations Support personnel will maintain control of the operation of equipment and controls associated with cask activities. Reasonable measures (e.g., initial drug testing,

! random drug screening, and continued observations of behavior) for the deterrence and early detection of personnel who are not fit to perform their duties are specified in VPAP-0105. Reasonable assurance is also provided that personnel are not under the influence of any illegal or legal substance, or mentally impaired from any cause, which in any way would adversely affect their ability to safely and competently perform their duties. Measures are also implemented to ensure station employees are medically fit to l perform their duties safely. All station personnel receive a baseline audiogram and visual test, and are grouped based upon the level and frequency of participation in the medical surveillance program specified in VPAP-1901.

l VPAP-0105 and VPAP-1901 define and implement the Medical Surveillance program

! requirements for station personnel. Copies of VPAP-0105 and VPAP-1901 are attached for your information.

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