ML20205G887

From kanterella
Jump to navigation Jump to search

Forwards RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, for Plant, Units 1 & 2.Response Requested within 60 Days of Date of Ltr
ML20205G887
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 04/02/1999
From: Nick Hilton
NRC (Affiliation Not Assigned)
To: Hutchinson C
ENTERGY OPERATIONS, INC.
References
GL-96-05, GL-96-5, TAC-M97013, TAC-M97014, NUDOCS 9904070410
Download: ML20205G887 (4)


Text

,.. .

MQ.k b c ' ( /~m\

= S UNITED STATES

  • NUCLEAR REGULATORY COMMIS810N WASHINGTON, D.C. tamaa anaq ,

,, g April 2, 1999 i Mr. C. Randy Hutchimon Vice President, Operations ANO Entergy Operatiens, Inc.

1448 S. R. 333 Russellville, AR 72801

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 96-05 PROGRAM AT ARKANSAS NUCLEAR ONE, UNITS 1 AND 2 (TAC NOS. M97013 AND M97014)

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

On March 17,1997, you submitted a response to GL 96-05 indicating your intent to implement the provisions of a Joint Owners Group (JOG) Program on MOV Periodic Verification. The NRC statt has encouraged licensees to participate in the industry-wide JOG program to provide

((r 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. ,

j On January 11,1999, you submitted an updated response to GL 96-05 that indicated that you / '

will continue to participate in the JOG MOV-Periodic Verification Program through its membership in the Boiling Water Reactor Owners Group (OG), Combustion Engineering OG, l and/or Babcock & Wilcox OG and will implement the program elements described in Topi::al '

Report NEDC-32719, Revision 2. 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 i ; quires only limited information to complete its GL 96-05 review for your facility.

l m.-,an7 N E 00EB]CQPy

{J'IM$ E$a

n j \

l C. R. Hutchinson April 2, 1999 Enclosed is a request for additional information (RAI) regarding your GL 96-05 program. The

- RAI was discussed with Mr. Steve Bennett and others of your staff on March 8,1999. A mutually agreeab!e target date for your response of 60 days from this letter's date of issue was established. If circumstances result in the need to revise the target date, please call me at the earliest opportunity.

Sincerely, M. Christopher Nolan for 1

Nicholas D. Hilton, Project Manager, Section 1  !

Project Directorate IV & Decommissioning l Division of Licensing Project Management l Office of Nuclear Reactor Regulation l

Docket Nos. 50-313 and 50-368 j

Enclosure:

As stated cc w/ encl: See next page l

DISTRIBUTION:

Docket File PUBLIC PDIV-1 r/f NHilton ~ CNolan LBerry ACRS KBrockman, RIV OGC JZwolinski/S'olack RGramm Document Name: G:\ANOFINAL\RAl97013.WPD _

OFC PDIVd/EM PDIV-1/PM PDIV-1/A PDIV-1/SC NAME NHi vw CNolan 1, Berry k RGramM DATE k/ \ /99 Y / / /99 / (/99 S/k/99 COPY YES/NO YES/NO hEShh YES/NO OFFICIAL RECORD COPV

FT r (j 1

Mr. C. Randy Hutchinson

(*

1 Entergy Operations, Inc. Arkansas Nuclear One, Units 1 & 2 cc:

Executive Vice President Vice President, Operations Support

& Chief Operating Officer Entergy Operations, Inc.

Entergy Operations, Inc. P. O. Box 31995 P. O. Box 31995 Jackson, MS 39286-1995 l Jackson, MS 39286-1995 Wise, Carter, Child & Caraway Director, Division of Radiation P. C. Box 651 Control and Emergency Management Jackson, MS 39205 Arkansas Department of Hoalth 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 Winston & Strawn 1400 L Street, N.W.

Washington, DC 20005-3502 Manager, Rockville Nuclear Licensing Framatone Technologies 1700 Rockville Pike, Suite 525 l Rockville, MD 20852 l

l Senior Resident inspector l U.S. Nuclear Regulatory Commission P. O. Box 310 i London, AR 72847 l

l Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 County Judge of Pope County Pope County Courthouse i Russellville, AR 72801 l

l l

1 i

l 1

.I

, .i-

, REQUEST FOR ADDITIONAL INFORMATION ON RESPONSE OF ARKANSAS NUCLEAR ONE. UNITS 1 AND 2 TO GENERIC LETTER 96-05

1. In NRC [ Nuclear Regulatory Commission) Inspection Report No. 50-313 and 368/96-23, the NRC staff closed its review of the motor-operated valve (MOV) program implemented at Arkansas Nuclear One, Units 1 and 2 (ANO) in response to Generic Letter (GL) 89-10,

" Safety-Related Motor-Operated Valve Testing and Surveillance." 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 neted that (1) the licensee was still evaluating dynamic unseating loads; (2) the licensee intended to perform modifications to increase the actuator capabilities for several valves that had less thah 10 percent margin; and (3) the licensae acknowledged the need to improve its trending procedures. Describe the actions taken to address the specific long-term aspects of the MOV program at ANO noted in the NRC inspection report.

2. In a letter dated Match 17,1997, the licensee stated that it is participating in the Joint Owners Group (JOG) Program on MOV Periodic Verification in response to GL 96-05. It is recognized that the owners group for ANO Unit 1 (a Babcock & Wilcox designed reactor) did not participate in the JOG program. On August 6,1997, the Combustion Engineering (CE)

Owners Group submitted Revision 2 of Topical Report MPR-1807 on the JOG Program on MOV Periodic Verification. On October 30,1937, the NRC staff completed a safety evaluation concluding that the JOG program is an acceptable industry-wide ~ response to GL 96-05, with cartain conditions and limitations.

The JOG program specifies that the methodology and discrimination criteria for ranking MOVs according to their safety significance are the responsibility of each participating licensee. In its letter dated March 17,1997, the licensee stated that static diagnostic testing would be based, in part, on an expert review and ANO's Probabilistic Safety Assessment (PSA). Describe the methodologies used for risk ranking MOVs at ANO in detail, including the specific high-risk MOVs at each ANO unit in responding to this request, the licensee might apply insights from the guidance provided in the Westinghouse Owners Group (WOG)

Engineering Report V-EC-1658-A (Revision 2, dated August 13,1998)," Risk Ranking Approach for Motor-Operated Valves in Response to Generic Letter 96-05," and the NRC safety evaluation dated April 14,1998, on the WOG methodology for risk ranking MOVs at Westinghouse designed reactors. The licensee could also obtain insights from an MOV risk-ranking methodology developed by the Boiling Water Reactor Owners Group.

3. The 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. Describe the plan at ANO for ensuring adequate ac and de MOV motor actuator output capability, including consideration of recent guidance in Limitorque Technical Update 98-01 and its Supplement 1.

Enclosure