ML20052G077
| ML20052G077 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/24/1982 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20052G051 | List: |
| References | |
| 50-259-82-06, 50-259-82-6, 50-260-82-06, 50-260-82-6, 50-296-82-06, 50-296-82-6, NUDOCS 8205140287 | |
| Download: ML20052G077 (3) | |
Text
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APPENDIX A NOTICE OF VIOLATION Tennessee Valley Authority Docket Nos. 50-259, 260, & 296 Brcs.3 Ferry 1, 2, and 3 License Nos. DPR-33, 52 & 68 As a result of the inspection conducted on December 26, 1981 - January 25, 1982, and in accordance with the Interim Enforcement Policy, 45 FR 66754 (October 7, 1980), the following violations were identified.
l A.
10 CFR 50.59(b) requires that the licensee shall maintain records of changes in the facility to the extent that such changes constitute changes in the facility as described in the safety analysis report. These records shall include a written safety evaluation which provides the basis for the determination that the changes do not involve an unreviewed safety question.
Contrary to the abcve, the requirements that a safety evaluation be performed on changes to the facility as described in the safety analysis report Section 9.3-1B was not met in that in January 7,1982 a flush hose was installed on the drain line from the 1.75 minute Off Gas Holdup Volume to the Off Gas Condensate Sump without a Maintenance Request (MR) form, a Temporary Alteration Control Fonn (TACF) nor a safety evaluatic'..
This modification resulted in a release of airborne activity in the Radwaste Building and the Service Building on January 10, 1982.
This is a Severity Level IV Violation (Supplement I.D.I.).
B.
10 CFR 50.55a,(g)(4) requires in part that, "throughout the service life of a boiling... water cooled nuclear power facility, components which are described as ASME Class 1, 2 and 3... shall meet the requirements set forth in Section XI of editions of the ASME Boiler and Vessel Code.
"Section XI of the ASME Boiler and Vessel code requires that Category A and B valves shall be stroke time tested.
l 4
l Contrary to the above, the requirements of ASME Section XI for stroke time l
testing of Category A and B, class 1, 2'and 3 valves, has not been met in l
that two Primary Containment Group 6 isolation valves for the containment Atmosphere Dilution System (FCV 84-19, FCV 84-20) have not been stroke time te sted.
This is a Severity Level V Violation (Supplement I.E.).
This is applicable to all units.
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C.
Technical Specification 6.3.a requires that detailed written procedures be l
prepared, approved, and adhered to for Radiation Control, Maintenance j
Operations, and Surveillance Instructions.
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Tennessee Valley Authority 2
Docket Nos. 50-259, 260 & 296 Notice of Violation License Nos. DPR-33, 52 & 68 Contrary to the above, detailed written procedures were not adhered to in that:
1.
On December 29, 1981, the 1-B Containment Atmospheric Monitor (CAM) pump was disconnected and removed from the CAM system without the issuance of a Special Work Permit (SWP) as required by Radiological Control Instruction (RCI)-10 when the contamination hazards for a particular job are unknown.
2.
As of January 8,1982 the inspector identified that the five year inspection of flood protection devices was not conducted as required by ikchanical Maintenance Instruction 19.
3.
On January 7,1982 two workers entered a radiation area to install scaffolding without an approved SWP as required by RCI-10,Section V. A. I.
4.
RCI-10 Section VIII, paragraph B requires that Special Work Permit -
Routine (RCI-9) not be used when the area is posted as a Special Work Permit area.
a.
On December 31, 1981 a Health Physics (H.P.) technician entered the Scram Discharge Instrument Volume (SDIV) area without signing in on the posted SWP for that area. The H.P. technician signed in on a SWP-Routine, b.
On January 18, 1982, a H.P. technician monitoring the installation of the equipment drain pump for Unit 2, on 519 level, North East quadrant entered without signing in on the posted SWP for that area.
He signed in on the SWP-Routine.
5.
WI.ile performing Surveillance Instruction (SI) 4.2.C.8, "Instrumenta-tion that initiate Rod Blocks Rod Sequence Control Restraints, First Stage Turbine Pressure", on January,1982, the following procedure steps were not adhered to; a.
Step 4.1.c specifies use of a 200 psi test gauge. A 500 psi test gauge was used.
b.
Step 4.2.a requires a digital volt meter to be used.
A volt-ohm meter was used.
c.
Step 4.2.a requires connecting the digital voltmeter to terminals 5 and 6 of the alarm unit.
The digital volt meter was connected to terminals CC79 and CC84.
This is a Severity Level V Violation (Supplement I.E.) and is applicable to i
all three units.
Pursuant to the provisions of 10 CFR 2.201, you are hereby required to submit to this office within thirty days of the date of this Notice, a written statement or
Tennessee Valley Authority 3
Docket Nos. 50-259, 260 & 296 Notice of Violation License Nos. DPR-33, 52 & 68 explanation in reply, including:
(1) admission or denial of the alleged viola-tions; (2) the reasons for the violations if admitted; (3) the corrective steps which have been taken and the results achieved; (4) corrective steps which will be taken to avoid further violations; and (5) the date when full compliance will be achieved.
Consideration may be given to extending your response time for good cause shown.
Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affirmation.
Date:
MAR 2 41982
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