ML20199B081

Forwards Request for Addl Info Re GL 96-05, Periodic Verification Design-Basis Capability of Safety-Related Motor-Operated Valves, to Request That NPP Licensees Establish Program Effectiveness of Current Program

ML20199B081
Person / Time
Site:	Browns Ferry
Issue date:	01/12/1999
From:	Raghavan L NRC (Affiliation Not Assigned)
To:	Scalice J TENNESSEE VALLEY AUTHORITY
References
GL-96-05, GL-96-5, TAC-M97020, TAC-M97021, TAC-M97022, NUDOCS 9901130219
Download: ML20199B081 (3)

Text

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, .. January 12, 1999

- Mr. J. A. Scalica Chi:f Nucl2cr Officar and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street i Chattanooga, Tennessee 37402-2801 l

SUBJECT:

BROWNS FERRY NUCLEAR PLANT, UNITS 2 AND 3 - REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 96-05 PROGRAM -(TAC NOS. M97020, M97021 AND M97022)  !

Dear Mr. Scalice:

On September 18,1996, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 96-05, " Periodic Verification of Design-Basis Capability of Safety-Reiated Motor-Operated Valves," to request that nuclear power plant licensees establish a program, or ensure the effectiveness of the current program, to verify on a periodic basis that safety-related metor- 1 operated valves (MOVs) continue to be capable of performing their safety functions within the ,

current licensing basis of the facility. l On April 28,1998, Tennessee Valley Authority (licensee of Browns Ferry Nuclear Plant, Units 1, 2 and 3) submitted an updated response to GL 96-05 indicating its intent to implement the provisions of a Joint Owners Group (JOG) Program on MOV Periodic Verification at l Browns Feny. The NRC staff has encouraged licensees to participate in the industry-wide JOG program to provide a benefit in reactor safety by sharing expertise and information on MOV

. performance and to increase the efficiency of GL 96-05 activities at nuclear plants. Licensee participation in the JOG program also minimizes the amount of information necessary for the NRC staff to review each licensee's response to GL 96-05. As a result, the NRC staff requires  ;

l limited information to complete its GL 96-05 review for Browns Ferry.

Please provide the required information described in the enclosure. This request was discussed with Mr. David Matherly of the Browns Ferry licensing staff on January 11,1999, and /

a target response date of March 31,1999, was agreed to. j Sincerely, Original si I#

L. Raghavan, bned benior hroject Manager Project Directorate 11-3 r(7I 9901130219 900112 ,

PDR ADOCK 05000259 Division of Reactor Proj,ects - 1/11 '

P PDR . Office of Nuclear Reactor Regulatior.

Docket Nos. 50-259, 50-260, 50-296

Enclosure:

Request for Additional i Information l cc w/ encl:. See next page (('j{j ~

kv.~m mY

_L!.2 pt ]<f DISTRlRUTION:

- C. Thomas ACRS TScarboro PUBLIC B. Clayton L. Plisco, Ril BFN-3 R/F L.Raghavan J. Zwolinski(A) OGC l DOCUMENT NAME: G:\BFN\RAl97020.WPD

. To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy

with ettachment/ enclosure "N" = No copy

• See previous concurrence l OFFICE- PM:POII-3 l LA:PDII 3 . jl D:Pyll-3 . ---- l l l i NAME LRaghavan W BClayton Af# M bipf V /

DATE 01/(1./99 01/ll/99 C1/7/_99

, , . Official Record Copy p30041

? .A I

Mr. J. A. Scalice - BROWNS FERRY NUCLEAR PLANT l Tennessee Valley Authority I cc:

Senior Vice President Mr. Mark J. Burzynski, Managar Nuclear Operations Nuclear Licensing )i Tennessee Valley Authority Tennessee Valley Authority i 6A Lookout Place 4X Blue Ridge l

1101 Market Street 1101 Market Street '

Chattanooga, TN 37402-2801 Chattanooga, TN 37402-2801 Mr. Jack A. Bailey, Vice President Mr. Timothy E. Abney, Manager Engineering & Technical Services Licensing and Industry Affairs Tennessee Valby Authority Browns Ferry Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Decatur, AL 35609 IAc. Karl W. Singer, Site Vice President Regional Administrator, Region 11 Browns Ferry Nuclear Plant U.S. Nuclear Regulatory Commission Tennessee Va' ley Authority 61 Forsyth Street, SW., Suite 23T85 P.O. Box 2000 Atlanta, GA 30303-3415 Decatur, AL 35609 Senior Resident inspector General Counsel U.S. Nuclear Regulatory Commission  ;

Tennessee Valley Authority Browns Ferry Nuclear Plant '

ET 10H 10833 Shaw Road 400 West Summit Hill Drive Athens, AL 35611 Knoxville, TN 37902 State Health Officer

_Mr. Raul R. Baron, General Manager Alabama Dept. of Public Health Nuclear Assurance 434 Moriroe Street Tennessee Valley Authority Montgomery, AL 36130-1701 SM Lookout Place 1101 Market Street . Chairman Chattanooga, TN 37402-2801 Limestone County Commission 310 West Washington Street Mr. Robert G. Jones, Plant Manager Athens, AL 35611 Browns Ferry Nuclear Plar,t Tennessee Valley Authority

- P.O. Box 2000 ,

Decatur, AL 35609 l

l

l ,

! REOUEST FOR xDDITIONAL INFORMATION REGARDING GENERIC LETTER 96-05 PROGRAM -

(TAC NOS. M97020. M97021 AND M97022

1. In NRC Inspection Report No. 50-259,260, & 296/98-05, the NRC staff closed its review of the motor-operated valve (MOV) program implemented at Browns Ferry Nuclear Plant (Browns Ferry) in response to Generic Letter (GL) 89-10, " Safety-Re!ated Motor-Operated Valve Testing and Surveillance," based on the results of the inspection and the licensee's actions to resolve outstanding MOV issues as described in a letter dated July 16,1998. In the inspection report, the NRC staff discussed certain aspects of the licensee's MOV program to be addressed over the long term. For example, the inspectors noted that (1) the licensee intends to use data from another licensee to justify the load sensitive behavior assumptions applied to MOVs with roller screw stem nuts; and (2) the licensee was developing a quantitative analysis to show that de MOVs would perform their design-basis functions within specified stroke time requirements. In addition, NRC Inspection Report No.

50-259,260, & 296/98-03 noted that the licensee had not completed revisions to the Unit 2 thrust calculations and setting drawings. Thera revisions were scheduled for completion by August 31,1998. The licensee should provide a summary status of actions taken to address the specific long-term aspects of the MOV progrcm at Browns Ferry noted in the NRC inspection reports and its letter dated July 16,1998.

2. The licensee indicates that its MOV static diagnostic periodic verification program will include test methods at the valve and the motor control center. Will diagnostic data be obtained for 211 GL 96-05 MOVs? If not, the licensee should describe its plans to monitor degradation in capability for those MOVs not diagnostically tested.

3. The licensee should briefly describe its plans for the use of test data from the motor control center (MCC) including (1) correlation of new MCC test data to existing direct force measurements; (2) interpretation of changes in MCC test data to changes in MOV thrust and torque performance; (3) considerstbn of system accuracies and sensitivities to MOV degradation for both output and operating performance requirements; and (4) validation of MOV operability using MCC testing.

4. The Joint Owners Group (JOG) program focuses on the potential age-related increase in the thrust or torque required to operate valves under their design-basis conditions. In the NRC safety evaluation dated October 30,1997, on the JOG program, the NRC staff specified that licensees are responsible for addressing the thrust or torque delivered by the MOV motor actuator and its potential degradation. In a letter dated April 28,1998, the licensee stated that potential actuator degradation would be identified through review and trending of actuator performance parameters. Further, NRC Inspection Report No. 50-259, 260, & 296/98 03 noted that the licensee was revising actuator output calculations for the close direction to include more conservative pullout efficiencies and an application factor of 0.90. However, Limitorque had not yet released its Technical Update 98-01 at the time of this inspection. Therefore, the licensee should provide the current status of actions at Browns Ferry for ensuring adequate ac and de MOV motor E.:tuator output capability, including consideration of recent guidance in Limitorque Technical Update 98-01 and its

, Supplement 1.

l l

Enclosure