L-88-004, Completion of NRC Bulletin 88-04, Potential Safety-Related Pump Loss

Completion of NRC Bulletin 88-04, Potential Safety-Related Pump Loss

ML041320342
Person / Time
Site:	Browns Ferry
Issue date:	05/07/2004
From:	Abney T Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation, NRC/RGN-II
References
BL-88-004
Download: ML041320342 (5)

Text

May 7, 2004 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN P1-35 Washington, D.C. 20555-0001 Gentlemen:

In the Matter of )

Docket No. 50-259 Tennessee Valley Authority )

BROWNS FERRY NUCLEAR PLANT (BFN) UNIT 1 - COMPLETION OF NRC BULLETIN 88-04, POTENTIAL SAFETY-RELATED PUMP LOSS This letter notifies NRC of the completion of NRC Bulletin 88-04, Potential Safety-Related Pump Loss" for BFN Unit 1.

On May 5, 1988, NRC issued Bulletin 88-04 to request all licensees to investigate and correct as applicable two miniflow design concerns. The first concern involved the potential for the dead-heading of one or more pumps in safety-related systems that have a miniflow line common to two or more pumps or other piping configurations that do not preclude pump-to-pump interaction during miniflow operation. The second concern was whether or not the installed miniflow capacity was adequate for single pump in operation.

The similarity of the boiling water reactor (BWR) designs prompted the BWR Owner's Group (BWROG) to prepare a generic response to Bulletin 88-04. TVA endorsed the BWROG position as stated in the BWROG letter (BWROG-8836) from D. N. Grace to the NRC dated June 29, 1988. The BWROG response was supplemented by plant-specific information for BFN. TVA responded to this Bulletin for BFN in References 1. TVA committed to verify the adequacy of the miniflow line sizes on BFN Unit 1 prior to restart. TVA also provided additional information for BFN Units 1 and 3 in Reference 2. NRC found TVAs response acceptable in Reference 3.

U.S. Nuclear Regulatory Commission Page 2 May 7, 2004 In summary, TVA evaluated the following BFN safety-related system pumps:

Residual Heat Removal including Low-Pressure Coolant Injection, Containment Spray Cooling, Suppression Pool Cooling and Shutdown Cooling; Emergency Equipment Cooling Water; Reactor Core Isolation Cooling; High Pressure Coolant Injection; Residual Heat Removal Service Water; and Core Spray.

The system-by-system evaluation included the review of design drawings, design data, surveillance test data, available maintenance history, and pump supplier information where available. Neither hardware nor procedural modifications were identified as a result of the BWROG and TVA's reviews.

TVA has since verified the adequacy of the miniflow line sizing for BFN Unit 1. The calculations have been completed and no problems with dead-heading or miniflow capacity were identified. Since the Bulletin 88-04 programmatic aspects were previously verified by NRC for BFN, the program does not have to be re-reviewed or re-verified. NRC inspection requirements for TVAs response to Bulletin 88-04 for BFN Unit 1 should focus on its implementation.

U.S. Nuclear Regulatory Commission Page 3 There are no new regulatory commitments associated with this submittal. If you have any questions, please contact me at (256) 729-2636.

I declare under penalty of perjury that the foregoing is true and correct. Executed on May 7, 2004 Sincerely, Original signed by:

T. E. Abney Manager of Licensing

References:

1. TVA letter, R. Gridley to NRC, Browns Ferry (BFN),

Watts Bar (WBN), and Bellefonte (BLN) Nuclear Plants -

NRC Bulletin (NRCB) 88-04, "Potential Safety-Related Pump Loss," dated September 30, 1988.

2. TVA letter, C.H. Fox to NRC, Browns Ferry Nuclear Plant (BFN) Units 1 and 3 - Additional Response to NRC Bulletin 88-04 (NRCB 88-04) - Potential Safety Related Pump Loss (TAC Nos. 69888, 69889, 69890), dated April 5, 1989.

3. NRC letter, S.C Black to O.D. Kingsley, Response to NRC Bulletin 88 Browns Ferry Nuclear Plant, Units 1 and 3 (TACs 69888, 69890), dated May 8, 1989.

cc: See Page 4

U.S. Nuclear Regulatory Commission Page 4 May 7, 2004 (Via NRC Electronic Distribution)

U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-3415 Mr. Stephen J. Cahill, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Senior Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, AL 35611-6970 Kahtan N. Jabbour, Senior Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)

One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739

U.S. Nuclear Regulatory Commission Page 5 May 7, 2004 SMK:BAB cc: M. J. Burzynski, BR 4X-C R. G. Jones, NAB 1A-BFN J. R. Rupert, NAB 1A-BFN K. W. Singer, LP 6A-C M. D. Skaggs, POB 2C-BFN J. Valente, NAB 1E-BFN EDMS S:lic/submit/subs/Safety Related Pump loss.doc