ML18024B081

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Responds to NRC Re Violation Noted in IE Insp Repts 50-259/79-24,50-260/79-24 & 50-296/79-24.Corrective Actions:Sensor Replaced
ML18024B081
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 10/16/1979
From: Mills L
TENNESSEE VALLEY AUTHORITY
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18024B080 List:
References
NUDOCS 7911130023
Download: ML18024B081 (6)


Text

TENNESSEE VALLEYAUTHORITY...

I CHATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II

)0 l'. 31 October 16, 1979 Mr. James PE O'Reilly, Director Office of Inspection and Enforcement U.ST Nuclear Regulatory Commission Region II Suit:e 3100 101 Marietta Street Atlanta, Georgia 30303

Dear Mr. O'Reilly:

Enclosed is our response to R.

CD Lewis'eptember 25, 1979, letter, RII:DSP 50-259/79-24, 50-260/79-24, and 50-296/79-24, concerning activities at Browns Ferry Nuclear Plant which appeared to be in noncompliance with NRC requirements.

We have reviewed the above inspection report and find no proprietary information in it.

Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Manager Nuclear Regulation and Safety Enclosure An Equai Opportunity Employer FQlrxee

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ENCLOSURE

RESPONSE

TO R.

C. LEWIS'ETTER DATED SEPTEMBER 25, 1979,

REFERENCE:

RII:DSP 50-259/79-24, 50-260/79-24, 50-296/79-24 INFRACTION As required by Technical Specification 6.7.2.b.(2),

conditions leading to operation in a degraded mode permitted by a limiting condition for operation shall be the subject of a 30-day written report to the director of the Region II office.

Contrary to the above, loss of the torus hydrogen monitor, which led to operating in a degraded mode permitted by Technical Specification 3.7.H.4, occurred during the period April 23-25 and was not reported to,the Region II office.

RESPONSE

Ex lanation The note included as a part of technical specification 6,7.2.b.(2) states that "Routine surveillance testing, instrument calibration, or preventative maintenance which require system configurations as described in items 2.b.(1) and 2.b.(2) need not be reported except where test results themselves reveal a degraded mode as described above."

The calibration performed under trouble report 128082 did not reveal a degraded mode of operation insomuch as the sensor did respond to the calibration gas and gave the correct signal for the applied concentration.

Following calibration, the sensor was returned to service.

Corrective.Ste s Taken and Results Achieved After the sensor was returned to service, the sensor continued operating with a gradual degradation over the next 12 days, at which time it was declared inoperable and reported to the NRC Region II office.

The sensor was replaced on May 14, 1979, during a cold shutdown for other reasons.

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Corrective Ste s Taken to Avoid Further Noncom liance Any calibrations required as a result of trouble reports will be reported to the NRC Region II office if, as a result of calibration, the plant is placed into a limiting condition for operation.

Date Full Com liancd Achieved The above interpretation of technical specification 6.7.2.b.(2) was established on October ll, 1979, and will continue from that date forward.

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