ML003723635

From kanterella
Jump to navigation Jump to search
Summary of May 23, 2000, Meeting with Entergy Regarding Equipment Qualification (EQ) Calculations Review for Arkansas Nuclear One Unit (ANO-1)
ML003723635
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 06/13/2000
From: Mitra S
NRC/NRR/DRIP/RLSB
To: Walters D
Nuclear Energy Institute
Mitra, SK, NRR/RLSB, 415-2783
References
Download: ML003723635 (7)


Text

June 13, 2000 LICENSEE: Entergy Operations, Inc (Entergy)

SUBJECT:

SUMMARY

OF MAY 23, 2000, MEETING WITH ENTERGY REGARDING EQUIPMENT QUALIFICATION (EQ) CALCULATIONS REVIEW FOR ARKANSAS NUCLEAR ONE UNIT 1 (ANO-1)

On May 23, 2000, representative of Entergy met with the Nuclear Regulatory Commission (NRC) staff and its contractor Brookhaven National Laboratory (BNL) representative to review EQ calculations. A list of meeting attendees is attached. The following calculations were reviewed by the staff and the contractor.

1. 4.4.1 Allis Chalmers Motors Allis Chalmers Report No. NQ7304852, NUS Calculation 84-EQ0034-01, dated November 21, 1984, and ANO-1 Environment Qualification Report Assessment (EQRA)

No. V02-001, Rev. 0, dated July 1, 1996.

2. 4.4.4 Anaconda EPR Insulated Instrumentation, Control/Power Cable Franklin Institute Research Laboratories Report F-C4350-4, dated July 1976, and EQRA No. V05-003, Rev. 1, dated October 6, 1998.
3. 4.4.9 Buchanan Terminal Blocks, Inside Reactor Building Limitorque Report No. B0119, Rev. 1 dated July 1, 1982, and EQRA No. V11-002, Rev. 0, dated July 1, 1996.
4. 4.4.10 Conax Thermocouples Conax Test Report No. IPS-1138, dated January 31, 1985, and EQRA No. V14-001, Rev. 0, dated July 1, 1996.
5. 4.4.11 Conax Resistance Temperature Detectors Conax Test Report No. IPS-875, Rev. A, dated March 9, 1983, and EQRA No. V14-002, Rev. 0, dated July 1, 1996.
6. 4.4.13 Conax Electrical Penetration Assemblies Franklin Report No. F-C4911-2, dated March 1978, ANO-1 Calculation 87-EQ-0002-29, Rev. 0, dated October 1, 1990, and EQRA No. V14-005, Rev. 0, dated July 1, 1996.

2 June 13, 2000

7. 4.4.21 Limitorque Motor Operated Valve Actuators; Alternating Current/Inside Reactor Building (most applications)

Limitorque Test Report No. B0058, dated January 11, 1980, and EQRA No. V33-001, Rev. 1, dated August 26, 1998.

8 4.4.31Okonite 600V Power Cable with Okonite Insulation and an Okolon Jacket (most applications)

Okonite Report No. NQRN 1A, Rev. 4, dated March 31, 1987, and EQRA No. V38-003, Rev.1, dated October 15, 1998 9 4.4.35 Raychem Cable Splice and Jacket Repair Tape (type NJRT)

Raychem Test Reports Nos. EDR-5210, Rev. 1, dated January 9, 1992, EDR-5046, Rev. 1, dated March 4, 1982, and EQRA No. V40-002, Rev. 1, dated September 1, 1999.

10. 4.4.38 Rockbestos Coaxial Cable (most applications)

Rockbestos Test Report No. QR-6802. dated March 12, 1986, and EQRA No. V42-001, Rev. 1, dated October 6, 1998.

11. 4.4.40 Rockbestos Firezone R Silicone Rubber High Temperature Cable (some applications)

Rockbestos Test Report No. QR-9801, Rev. 0, dated January 24, 1991, ANO-1 Engineering Report No. 93R-1026-01, Rev. 4, dated September 5, 1997, and EQRA No. V42-003, Rev. 1, dated October 6, 1998.

12. 4.4.58 Brand Rex Cross-Linked Polyethylene Coaxial Cable Franklin Institute Research Laboratories Test Report No. F-C5120-2, dated September 2, 1980, Calculation No. 94EQ-0001-01, Rev. 0, dated June 6, 1996, and EQRA No. V55-001, Rev. 2, dated September 3, 1999.

The review of the following EQ calculations are summarized as follows:

1. 4.4.48Target Rock Solenoid Operated Valves (Reports 2375 and 1827)

The staff and its contractor reviewed Target Rock Test Report No. 2375, Rev. G, dated May 4, 1983, ANO-1 Calculation 90-EQ-1001-02, Rev. 0, dated June 4, 1990, and EQRA No. V46-007, Rev. 0 dated July 1, 1996, and found that two solenoid valves would have peak temperature of 207-F. The applicant indicated that those two valves had a qualified life of 30 years and would be replaced before 30 years and hence they were excluded from the license renewal application.

3 June 13, 2000

2. 4.4.55 Westinghouse Motors, Models TBFC and SBDP The staff and its contractor reviewed Test Report No. SCE-ANO-02, Rev. 2, dated July 1986, and EQRA No. V50-004, Rev. 0, dated July 1, 1996, and found that the applicants analysis did not consider the aging effect of non-operation of the motor at 105-F (motor ambient temperature). These motors are not running during normal operation. The applicant stated that they would address this finding as a RAI response.

/RA/

Sikhindra K. Mitra, Project Manager License Renewal and Standardization Branch Division of Regulatory Improvement Program Office of Nuclear Reactor Regulation Docket No. 50-313

Attachment:

List of Attendees cc w/attachment: See next page

3 June 13, 2000

2. 4.4.55 Westinghouse Motors, Models TBFC and SBDP The staff and its contractor reviewed Test Report No. SCE-ANO-02, Rev. 2, dated July 1986, and EQRA No. V50-004, Rev. 0, dated July 1, 1996, and found that the applicants analysis did not consider the aging effect of non-operation of the motor at 105-F (motor ambient temperature). These motors are not running during normal operation. The applicant stated that they would address this finding as a RAI response.

/RA/

Sikhindra K. Mitra, Project Manager License Renewal and Standardization Branch Division of Regulatory Improvement Program Office of Nuclear Reactor Regulation Docket No. 50-313

Attachment:

List of Attendees cc w/attachment: See next page DISTRIBUTION:

See attached page

  • See previous concurrence DOCUMENT NAME: G:\RLSB\MITRA\EQMEETING

SUMMARY

.WPD OFFICE LA:DRIP PM:RLSB:DRIP SC: EEIB:DE BC:RLSB:DRIP NAME EHylton* SKMitra* DFThatcher* CIGrimes*

DATE 06/02/00 06/12/00 06/12/00 06/13/00 OFFICIAL RECORD COPY

NRC MEETING WITH ENTERGY TO REVIEW EQUIPMENT QUALIFICATION CALCULATIONS FOR ARKANSAS NUCLEAR ONE UNIT 1, ATTENDANCE LIST MAY 23, 2000 NAME ORGANIZATION B. STIENMAN ENTERGY R. LOFARO BNL A. PAL NRC/NRR/DE/EEIB D. NGUYEN NRC/NRR/DE/EEIB P. SHEMANSKI NRC/NRR/DE/EEIB J. VORA NRC/RES/DET/MEB D. THATCHER NRC/NRR/DE/EEIB S. MITRA NRC/NRR/DRIP/RLSB Attachment

DISTRIBUTION:

HARD COPY RLSB RF E. Hylton E-MAIL:

R. Zimmerman J. Johnson D. Matthews S. Newberry C. Grimes C. Carpenter B. Zalcman J. Strosnider R. Wessman G. Bagchi K. Manoly W. Bateman J. Calvo J. Shea G. Holahan T. Collins C. Gratton B. Boger J. Peralta J. Moore J. Rutberg R. Weisman B. Poole M. Mayfield S. Bahadur A. Murphy W. McDowell S. Droggitis N. Dudley, ACRS RLSB Staff T. Kenyon M. Nolan P. Harrell (RIV)

C. Hackney J. Vora K. Kennedy, R IV

Arkansas Nuclear One Docket No. 50-313 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 Jackson, MS 39286-1995 Director, Division of Radiation Wise, Carter, Child & Caraway Control and Emergency Management P. O. Box 651 Arkansas Department of Health Jackson, MS 39205 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 Winston & Strawn Regional Administrator, Region IV 1400 L Street, N.W. U.S. Nuclear Regulatory Commission Washington, DC 20005-3502 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 Manager, Rockville Nuclear Licensing County Judge of Pope County Framatone Technologies Pope County Courthouse 1700 Rockville Pike, Suite 525 Russellville, AR 72801 Rockville, MD 20852 Mr. Douglas J. Walters Senior Resident Inspector Nuclear Energy Institute U.S. Nuclear Regulatory Commission 1776 I Street, N.W., Suite 400 P. O. Box 310 Washington, DC 20006-3708 London, AR 72847 DJW@NEI.ORG Mr. Doug Levanway Mr. Garry Young 600 Heritage Blvd. Entergy Operations, Inc.

Jackson, MS 39201 Arkansas Nuclear One 1448 SR 333 GSB-2E Russellville, Arkansas 72802 gyoung4@entergy.com