GNRO-2003/00063, Special Report 2003-001, Invalid Actuation of High Pressure Core Spray (HPCS)

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Special Report 2003-001, Invalid Actuation of High Pressure Core Spray (HPCS)
ML033240175
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 11/18/2003
From: Roberts J
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2003/00063 Special Report 03-001
Download: ML033240175 (2)


Text

Waterloo Road P.O. Box 756 Port Gibson, MS 39150 Tel601 437 6470 Director Nuclear Safety Assurance November 18,2003 U S . Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk

Subject:

Special Report Number 2003-001 Invalid Actuation of High Pressure Core Spray (HPCS)

Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29 GNRO-2003/00063 Sir or Madam:

The Grand Gulf Nuclear Station Technical Requirements Manual (TRM) 7.7.2.1 states: In the event an ECCS system is actuated and injects water into the Reactor Coolant System during MODES 1, 2, or 3, a Special Report shall be prepared and submitted to the Commission within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.

The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70. This Special Report is being submitted pursuant to TRM 7.7.2.1.

Discussion:

On September 27, 2003, at 0118 hours0.00137 days <br />0.0328 hours <br />1.951058e-4 weeks <br />4.4899e-5 months <br /> Central Time, while operating at approximately 100 percent power, Grand Gulf Nuclear Station experienced an invalid actuation of the High Pressure Core Spray (HPCS) System. The invalid signal was the result of an error made while performing a continuity check during a quarterly surveillance. Details can be found in Event Notification Number 40266.

This is the seventeenth cycle of the HPCS system experienced at GGNS at rated temperature and pressure. The operating usage factor increase for safety injection nozzles is very small e0.02) for each operating cycle. The operating usage factors for safety injection nozzles is approximately 0.3, which is significantly below 0.70, the level which must be reported to the NRC per the requirements of TRM 7.7.2.1.

N o v e m b e r 18, 2 0 0 3 GNRO-2003/00063 Page 2 of 2 Should you have any questions regarding this issue or require additional information, please contact Bill Abraham at (601) 437-2319.

Yours truly, JCWWBA cc:

Hoeg I T. L. I (GGNS Senior Resident) I (w/a)

Levanwav I D. E. 1 /Wise Carter) I /w/a)

Reynolds N. S. &/a j Smith L. J. (Wise Carter) (w/a)

Thomas H. L. (WW U.S.Nuclear Regulatory Commission ATTN: Mr. Bruce Mallett (w/2) 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 U S . Nuclear Regulatory Commission ATTN: Mr. Bhalchandra Vaidya, NRR/DLPM (w/2)

ATTN: FOR ADDRESSEE ONLY ATTN: U.S. Postal Delivery Address Only Mail Stop OWFN/7D-I Washington, D.C. 20555-0001