ML18026A952

Requests Submittal of Change to Tech Specs to Include Instrument Lines in Type a Tests or Proposal of Alternative Means to Ensure Lines & Valves Included in Type a Tests. Response Requested within 90 Days

ML18026A952
Person / Time
Site:	Browns Ferry
Issue date:	04/20/1984
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Parris H TENNESSEE VALLEY AUTHORITY
Shared Package
ML18026A953	List: ML18026A952
References
NUDOCS 8405040155
Download: ML18026A952 (6)

Text

April 20, 1984 Docket No. 50-260 Mr. Hugh G. Parris Manager of Power Tennessee Valley Authority 500 Chestnut Street, Tower II Chattanooga, Tennessee 37401

Dear Mr. Parris:

DISTRIBUTION NRC PDR Local PDR ORB82 Reading DEisenhut OELD EJordan JNGrace RClark SNorris ACRS (10)

Gray File

SUBJECT:

BROWNS FERRY UNIT 2 INTEGRATED LEAK RATE TEST FAILURE During the primary containment integrated leak rate (Type A) test at Browns Ferry Unit 2 on February 15 - 19,

1983, a leakage of 3 wt., X per day was observed.

This exceeded the acceptance limit of 1.5 wt. I per day.

The leakage path was identified as a valve flange which is not locally (Type B) testable.

After torquing the valve flange bolts the integrated test was completed with a measured leakage of 0.5 wt.

X per day.

This event was initially described in BFRO-50-26/8505, transmitted by your letter of March 16, 1983.

A summary report of the containment integrated leak rate test (CILRT) was transmitted by your letter of May 16, 1983.

A supplement to your initial reportable occurrence report was submitted by your letter of December 22, 1983.

The CILRT was witnessed by an inspector from Region II.

The inspection was documented in inspection report 50-259/260/296-83-06 sent to you on March 30, 1983.

A follow-up inspection was documented in inspection reports 50-259/260/296-83-56 sent to you by our letter dated January 17, 1984.

As indicated in the inspection reports, the integrated leak rate test is considered a failed test in accordance with the requirements of Paragraph III.A.lof Appendix J to 10 CFR 50.

This is the first failed test for Browns Ferry Unit 2.

Technical, Specification 4.7.2 and Paragraph III.A.6 of Appendix J require that if any perodic Type A test fails to meet the applicable acceptance criteria, the test schedule for subsequent Type A tests will be reviewed and approved by the Commission.

We have evaluated the CILRT, the corrective actions you have taken and the commitments you have made for future corrective actions.

Our Safety Evaluation is enclosed.

In your report of December 22, 1983, you committed to modify the flange that was leaking and all similar flanges in all three Browns Ferry units to permit local leak testing (Type B) of the flange gaskets for leakage.

You stated that these modifications have been completed on Unit 1 and will be completed on Unit 3 during the current outage.

You further committed to complete the modifications on Unit 2 during the Cycle 5 outage, tentatively scheduled to start August 24, 1984.

In view of your commitments and corrective actions, we have determined that no change in the Type A test schedule is required at this time.

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As discussed in the enclosed Safety Evaluation and in the inspection reports, certain instrument lines that would be exposed to post-accident containment pressure were isolated from the CILRT and had not been included in the leak test program at Browns Ferry.

Twenty-seven instrumentation valves and their associated piping, forming part of the reactor protection system at Browns Ferry Unit 2, were subsequently locally leak tested at accident pressure and exhibited leakage within acceptable limits.

Our position on this issue is that these instrument lines are considered to be an extension of the primary containment boundary and should be 'included in the integrated leak rate tests conducted at each of the Browns Ferry Units.

On page 4 of your May 16, 1983 report, you stated that these valves and associated tubing will be included in Type A tests by aligning the valves to directly see the CILRT test pressure.

Implementation of your commitments should lead to final resolution of this concern.

Therefore, you are requested to either submit a change to the Technical Specifications to include these lines in Type A tests or to propose an alternative means that will ensure the instrument lines and valves are included in the Type A tests.

Within 90 days of receipt of this letter, you are requested to address the approach you propose.

This request for additional information is specific to one licensee.

The reporting and/or recordkeeping requirements contained in this letter effect fewer than ten respondents; therefore OMB cleareance is not required under P.L.96-511.

Sincerely,

Enclosure:

As stated Original Signed by /

Domenic B. Vassallo, Chief Operating Reactors Branch P2 Division of Licensing cc w/enclosure:

See next page DL:ORB 2 SNo as;jk 04//g/84 D.R82 RC1 ar 04/ P /84 DL:ORBP2 DVassallo 04/ l3/84

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Mr. Hugh G. Parris Tennessee Valley Authority Browns. Ferry Nuclear Plant, Units 1, 2 and 3

CC:

H. S. Sanger, Jr., Esquire General Counsel Tennessee Valley Authority 400 Commerce Avenue E 11B 330 Knoxville,'ennessee 37902 Mr. Ron Rogers Tennessee Valley Authority 400 Chestnut Street, Tower II Chattanooga, Tennessee 37401 Mr. Charles R. Christopher

Chairman, Limestone County Commission Post Office Box 188

Athens, Alabama 35611 Ira L. Myers, M. D.

State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36130 Mr. H. N. Culver 249A HBD 400 Commerce Avenue Tennessee Valley Authority Knoxville, Tennessee 37902 U. S. Environmental Protection Agency Region IV Office

'Regional Radiation Representative 345 Courtland Street, N.

W.

Atlanta, Georgia 30308 Resident Inspector U. S. Nuclear Regulatory Commission Route 2, Box 311

Athens, Alabama 35611 Mr. Donald L. Williams, Jr.

Tennessee Valley Authority 400 West Sum'mit Hill Drive, W10885 Knoxville, Tennessee 37902 George Jones Tennessee Valley Authority Post Office Box 2000

Decatur, Alabama 35602

. Mr. Oliver. Havens U.

S'. Nuclear Regulatory Commission Reactor Training Center Osborne Office Center, Suite 200 Chattanooga, Tennessee 37411 James P. O'Reilly Regional Administrator Region II Office U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303