ML18033B590

From kanterella
Jump to navigation Jump to search
Notice of Violation from Insp on 901016-1116.Violation Noted:On 901020, Unit 3 Rwcs Valve 3-FCV-69-01 Unexpectedly Isolated During Momentary Power Loss, Contrary to Tech Spec 3.11.A.1
ML18033B590
Person / Time
Site: Browns Ferry  
Issue date: 12/17/1990
From: Wilson B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML18033B589 List:
References
50-259-90-33, 50-260-90-33, 50-296-90-33, NUDOCS 9012280317
Download: ML18033B590 (4)


Text

ENCLOSURE 1

NOTICE OF VIOLATION Tennessee Valley Authority Browns Ferry 1, 2, 8

3 Docket Nos. 50-259,

260, 8

296 License Nos.

DPR-33, 52, 8

68 During the Nuclear Regulatory Commission (NRC) inspection conducted on October 16 - November 16, 1990, violations of NRC requirements were identified.

The first violation involved failures to notify the NRC of reportable events in accordance with 10 CFR 50.72 and 50.73.

The second violation was for failure to take corrective action for a previous nonconformance.

In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C

( 1990), the violations are listed below:

10 CFR 50 requires notification and reporting to the NRC of various reactor events.

10 CFR 50.72 requires that licensee's notify the NRC within four hours of any event or condition that results in manual or automatic actuation of any Engineered Safety Feature (ESF).

10 CFR 50.73 requires that a Licensee Event Report (LER) be submitted within 30 days after the discovery of any operation or condition prohibited by the plant,'s Technical Specifications (TS).

Final Safety Analysis Report (FSAR) section 1.6.2, Nuclear Safety Systems and Engineered Safeguards, includes both the Primary Containment Isolation Control System (PCIS) and Secondary Containment..

The PCIS automatically initiates closure of isolation valves to seal off all potential leakage paths for radioactive material to the environs.

TS section

3. 11.A. 1 requires that the fire detection instrumentation listed in TS Table 3. 11.A be operable whenever equipment protected by the fire detection instrument is required to be operable.

TS section

3. 11.A.l.a requires that the fire detection system's heat and smoke detectors for all protected zones be operable and TS section 3.11.A.l.b requires that a patrolling fire watch be established whenever TS section 3.1l.l.a cannot be met.

Contrary to the

above, the licensee failed to notify the NRC within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of the ESF actuations in a,and b, below, and failed to submit an LER within 30 days for item c below.

a ~

On October 20,

1990, Unit 3

Reactor Water Cleanup system valve 3-FCV-69-01, a

PCIS valve, unexpectedly isolated during a momentary power loss from an electrical board transfer.

This valve is designed to isolate on a

PCIS group 3 actuation signal.

The licensee did not notify the NRC Operations Center of this unplanned ESF actuation via the Emergency Notification System until October 30, 1990.

9022280317 902217 PDR ADQCK 05000259 G

PDR

Tennessee Valley Authority Browns Ferry 1, 2, 5

3 Docket Nos. 50-259,

260, 5 296 License Nos.

DPR-33, 52, 5 68 b.

On November 4,

1990, the Refuel Zone ventilation system isolated due to a failed relay in the circuit for the refueling floor static pressure relays.

This ventilation system is designed to isolate upon receipt of =a PCIS group 6 actuation signal.

The licensee did not notify the. NRC Operations Center of this unplanned ESF actuation.

co On September 27,

1990, a patrolling fire watch missed the hourly check of the A 4160V shutdown board room due to the vital door being locked during a loss of the security card reading system.

The fire watch was required because the duct detector in the room would not actuate the associated dampers as required by TS Table 3.11.A.

The licensee did not submit an LER to the NRC on this event.

These examples are a Severity Level IV violation (Supplement I) which is appl icabl e to a l 1 three

- Units.

Pursuant to the provisions of 10 CFR 2.201, you are hereby required to submit a

written statement or explanation to the Nuclear Regulatory Commission, ATTN:

Document Control

Desk, Washington, DC 20555, with a

copy to the Regional Administrator, Region II, and a

copy to the NRC Resident Inspector, Browns Ferry, within 30 days of the date of the letter transmitting this Notice.

This reply should be clearly marked as a "Reply to a Notice of Violation" and should include:

( 1) admission or denial of the violation, (2) the reason for the violation if admitted, (3) the corrective steps which have been taken and the results. achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved.

Where good cause is shown, consideration will be given to extending the response time.

FOR THE NUCLEAR REGULATORY COMMISSION ruce A. Wilson, Chief TVA Projects Dated at Atlanta, Georgia this I'l~ day of December 1990

0