ML20058B903
| ML20058B903 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/04/1982 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20058B817 | List: |
| References | |
| 50-259-82-16, 50-260-82-16, 50-296-82-16, NUDOCS 8207260191 | |
| Download: ML20058B903 (2) | |
Text
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y-APPENDIX A NOTICE OF VIOLATION i
Tennessee Valley Authority Docket Nos. 50-259, 260, & 296 Browns Ferry 1, 2, and 3 License Nos. DPR-33, 52, & 68 As a result of the inspection conducted on May 12-19, 1982, and in accordance with the NRC Enforcement Policy, 47 FR 9987 (March 9, 1982), the following 4
violations were identi fied.
A.
Technical Specification 3.5.E.2 requires that if the High Pressure Coolant Injection (HPCI) system is inoperable, the reactor may remain in operation for a period not to exceed seven days, provided the Automatic Depressuri-zation System (ADS), Core Spray System (CSS), Residual Heat Removal System
[ Low Pressure Coolant Injection (LPCI) mode] and Reactor Core -Isolation Cooling (RCIC) are operable.
Contrary to the above, the requirement that the CSS and RHRS be operable if HPCI is inoperable was not met on May 12, 1982, in that the 1A Core Spray (CS) pump and the 1A Residual Heat Removal (RHR) pump had-their respective 4
i breakers racked out, rendering the pumps inoperable, while the HPCI system was inoperable for surveillance testing of the HPCI room temperature indicators.
This is a Severity Level IV Violation.(Supplement 1.D.2.) and applicable to Unit 1.
B.
Technical Specification 6.3. A requires that detailed written procedures i
shall be prepared, approved, and adhered to for normal operation of all systems and components involving nuclear safety of the facility.
Contrary to the above, the requirement that detailed procedures be prepared and adhered to for operation of components of systems involving nuclear safety was not met in that:
1.
The Shift Engineer was not informed as required by Standard Practice 12-17, Administrative Controls for Plant Operations, that the test i
conducted on the "A"
4kV shutdown board, per Specific Maintenance l
Instruction-1, on May 12, 1982, involved racking out the breakers for the 1A and 2A RHR pumps and the 1A and 2A core spray pumps.
2.
A procedure had not. been issued to implement TVA's December 23, 1980, l
response to TMI Action Item I.C.6, paragraph 4 which stated that l
equipment status would not be changed without approval of the reactor l
operator.
This is a Severity Level IV Violation (Supplement I.D.2.) and is applicable
(
to Unit 1 and 2.
I 8207260191 820715 i
PDR ADOCK 05000259 0
Tennessee Valley Authority 2
Docket Nos. 50-259, 260, & 296 Notice of Violation License Nos. OPR-33, 52, & 68
)
Pursuant to the provisions of 10 CFR 2.201, you are hereby required to submit to this of fice within thirty days of the date of this Notice, a written statement or 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 f urthe,' violations; and (5) the date when full compliance will be achieved. Consideration may be given to extending your response time for good cause shown.
Date:
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