ML18031B072
| ML18031B072 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/04/1986 |
| From: | Zech G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18031B071 | List: |
| References | |
| 50-259-86-32, 50-260-86-32, 50-296-86-32, NUDOCS 8612150160 | |
| Download: ML18031B072 (3) | |
Text
ENCLOSURE 1
NOTICE OF VIOLATION Tennessee Valley Authority Browns Ferry 1, 2, and 3
Docket Nos.
50-259, 50-260, and 50-296 License Nos.
DPR-33, DPR-52, and DPR-68 During the Nuclear Regulatory Commission (NRC) inspection conducted on September 1-30,
- 1986, two violations of NRC requirements were identified.
The violations involved failure to have adequate procedures as required by Technical Specifications and failure to adhere to procedures as required by 10 CFR 50, Appendix B.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions."
10 CFR Part 2, Appendix C (1985),
the violations are listed below:
A.
requires that detailed written procedures covering surveillance requirements shall be prepared, approved and adhered to.
Surveillance Requirement 4.7.E.2.a requires in part that the Control Room Emergency Ventilation System flow r ate shall be shown to be within +
10%
design flow when tested in accordance with ANSI N510-1975 at the specified intervals.
ANSI "N510-1975 requires that a pitot-tube velocity-traverse be made in accordance with Section 9 of American Conference of Government Industrial Hygieni sts (ACGIH) "Industrial Ventilation" manual at a point in the duct where airflow velocity is 1,000 fpm or more If there is no place where the airflow is greater than 1,000
- fpm, use one of the other methods as described in Section 9 of the ACGIH "Industrial Ventilation" manual.
Contrary to the
- above, Surveillance Instruction 4.7.E.5, Control Room Emergency Ventilation System Flow Rate Test, does not adequately satisfy the requirements in that a pitot-tube velocity-traverse is specified as an acceptable method of flow rate testing even though there is no place in the duct where the airflow is greater than 1,000 fpm.
This is a Severity Level V Violation (Supplement I) and is applicable to all units.
B.
10 CFR 50 Appendix B Criterion V requires that activities affecting quality be accomplished in accordance with prescribed instructions, procedures, or drawings.
Browns Ferry Standard Practice 10.9, Handling of Test Deficiencies, which implements the Nuclear guality Assurance
- Manual, Part II, Section 4.9, requires equipment deficiencies during a
test or surveillance instruction be documented and included along with the final disposition as part of the documentation package for the test being performed.
8612150160 861204 PDR
- DOCK 05000259 9
Tennessee Valley Authority Brow'ns Ferry 1, 2, and 3
2 Docket Nos.
50-259, 50-260,
& 50-296 License Nos.
DPR-33, DPR-52, and DPR-68 Contrary to the
- above, this requirement was not met in that equipment malfunctions observed during the performance of Surveillance Instruction (SI) 4.5.C. 1 (4),
Emergency Equipment Cooling Water (EECW) Annual Flow-rate
- Test, on August 22,
- 1986, were not identified or documented as part of the completed documentation package.
During the SI the EECW cross-'connect valves to the Reactor Building Closed Cooling Water System heat exchangers (67-50) did not open as expected.
The Unit 1 valve did not open.
The Unit 2 valve only opened to an intermediate position.
Flow through these valves was considered part of the normally assigned flow path of technical specification surveillance requirement 4.5.C. 1.6.
The SI was repeated on September 2,
1986.
The 'Unit 1 valve was found out of adjustment as documented on Maintenance Request (MR) 755513.
The Unit 2
valve had a
stuck solenoid in the control circuit for the valve as documented on MR 753912.
Final Safety Analysis Report Section
- 10. 10.3 states these valves are designed to open upon loss of raw cooling water pressure and close on low header pressure to guarantee flow to the emergency equipment components.
This is a Severity Level V Violation (Supplement I) and is applicable to all three units.
t Pursuant to the provisions of 10 CFR 2.201; Tennessee Valley Authority is hereby required to submit to this Office within 30 days of the date of the letter transmitting this Notice a written statement or explanation in reply including (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 w'i 11 be given to extending the response time.
FOR THE NUCLEAR REGULATORY COMMISSION ORIGINALSIGNED BY
( GARYG.ZECH Gary G. Zech, Director Division of TVA Projects
'ated at Atlanta, Georgia this 4th day of December 1986