ELV-02089, Advises of Plans to Discontinue Submittal of Leak Rate Rept After Each Refueling Outage in Future

Advises of Plans to Discontinue Submittal of Leak Rate Rept After Each Refueling Outage in Future

ML20058G631
Person / Time
Site:	Vogtle
Issue date:	11/02/1990
From:	Hairston W GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-3.D.1.1, TASK-TM ELV-02089, ELV-2089, NUDOCS 9011130319
Download: ML20058G631 (2)

Text

f i e* -, Georga rowur Company i *

• 333 hedmont Aenue Art:nta. Georg.a 30308

o. ' . lei: photo A04 526 3195 Mahng Address 40 InMntsa Center Parkwav Post Offee Box 1?95 Dirminghattt Alat ama 3520' To'ephone P05 liC8 558t November 2, 1990 o

w. o. Heiriton, "'

. senior Vce President ELV-02089

{ Nuclear Operations 0590 Docket Nos. 50-424 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk

< Washington, D. C. 20555 Gentlemen:

V0GTLE ELECTRIC GENERATING PLANT LEAKAGE OUTSIDE CONTAINMENT Technical Specification 6.7.4a states that a program to reduce leakage from those portions of systems outside of containment that could contain highly radioactive fluids during a serious transient or accident shall be established, I implemented and maintained. The program shall include leak test requirements for each system listed in 6.7.4a at refueling cycle intervals or less. This requirement is derived from NUREG-0737, THI Action item Ill.D.l.I.

Procedure 83202-C, " Leakage Assessment Program" implements the requirements of Specification 6.7.4a at Plant Vogtle. If leakage _is found, a Deficiency Card (OC) and/or. Maintenance Work Order (MWO) is to be issued to reduce leakage to as-low-as-practical levels. Section 5.0 of Procedure 83202-0 lists each system to be tested and references the procedure which is to be used to test each system. For example, Engineering Procedure 84203-1 is to be used for residual heat removal system leakage assessment. This procedure calls for a system walkdown and a visual inspection of each valve and its surrounding area, all caps, flanges and instrument lines, and all pumps, pump seals, heat exchangers, drains, vents and their surrounding areas for evidence of leakage.

Procedure 84204-1 addresses leakage assessment of the gaseous waste processing I system. . This procedure calls for the use of.a leak rate monitor, with leak rate i data recorded at 5 minute intervals for a period of 20 minutes. If a leak rate

~

in excess of 200 SCCM is -indicated, a soap bubble test and/or helium leak test is .to be performed on valves, flanges, joints,'etc. and corrective action taken 4

. to reduce leakage to as-low-as-practical levels. j TMI Action item III.D.l.1 (NUREG-0737) states that the leakage assessment program'shall include the following:

1. Immediate leak reduction'- Implement all practical leak reduction measures for all systems that could carry radioactive fluid outside of containment. Measure actual leakage rates with systems in operation and report them to the NRC. i b l 9011130319 901102 DR ADOCK 0500g 4 , [h g

c -

'\9 ,

c .> ,

l Georgia lbwer L U. S. Nuclear Regulatory Commission ELV-02089 Page 2

2. Continuing leak reduction - Establish and implement a program of preventive maintenance to reduce leakage to as-low-as-practical levels.

This program shall include periodic leak tests at intervals not to exceed each refueling cycle.

Item I was satisited by submittal of SL-2109, dated March 9,1987 for Unit 1, and GN-1586, dated March 27, 1989 for Unit 2. These reports presented measured leak rate data for each of the subject systems with a commitment to reduce all known leakage to as-low-as-practical levels, item 2 is satisfied by the Leakage Assessment Program as implemented by Procedure 83202-C. The intent of TMI Action Item 111.D.1.1 is to reduce leakage '

from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as-low-as-practical levels.

Our program accomplishes this requirement. Even though plant procedures have been established and ensure the systems are checked for leaks during each refueling outage, as plant personnel make rounds through the plant, leaks are noted and MW0s and/or DCs are written to ensure the leaks are fixed, in many ,

cases before the next refueling outage.

In response to-1MI Action Item Ill.D.l.1, Georgia Power Company (GPC) submitted letter GN-1029 dated August 5, 1986, in which GPC committed to report leak rate results to-the NRC at the end of each refueling outage in which testing takes place. Based on the above discussions and since this action item does not require a leak rate report be submitted to the NRC after each refueling outage GPC does not plan to submit such a report in the future.

Should you have any questions, please inquire.

Sincerely, x).A.L W r W. G. Hairston, 111  !

I WGH,Ill/PAH/gm xc: Georaia Power Company Mr. C. K. McCoy Mr. W. B. Shipman Mr. R. M. Odom Mr'. P. D. Rushton NORMS U. S. Nuclear Reaulatory Commission Mr. S. D. Ebneter, Regional Administrator Mr. D. S. Hood, Licensing Project Manager, NRR Mr. 8. R. Bonser, Senior Resident Inspector, Vogtle

_ _ _ _ _