ML20149L327
| ML20149L327 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 07/25/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20149L321 | List: |
| References | |
| 50-445-97-12, 50-446-97-12, NUDOCS 9707310276 | |
| Download: ML20149L327 (1) | |
Text
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Notice of Violation Contrary to the above, the licensee failed to provide measures to ensure that a i
condition adverse to quality was prompth/ dentified and corrected and, in the fourth i
example, to determine the cause and take corrective actions foi a significant condition adverse to quality.
1.
On May 14,1996, the Unit 2 safety injection system Train A Relief Valve 2-8853A was found leaking and was subsequently replaced; however, an operation, notification, and evaluation form was not initiated to evaluate the occurrence.
2.
In March 1996, the diaphragm for the reactor Makeup Water Pump Discharge Valve 2DD-0019 failed and was replaced under Work Request 3-95-322110-01; however, an operation, notification, and evaluation forre cas not initiated to evaluate the occurrence.
3.
Between July 6,1994, and May 6,1996, the licensee identified seven instances where diaphragm valves had failed or were in danger of failing because an internal fingerplate was installed upside down. However, the licensee did not take action to identify the location of each potentially improperly installed diaphragm valve and either inspect the valves or evaluate i
the adequacy of the installed configuration.
4.
Within Plant incident Report 96-055, the licensee identified numerous previous licensee failures to properly assess a slow closure condition of i
Feedwater Isolation Valve 1-HV-2315. This significant condition adverse to j
quality was identified by the licensee and reported within Plant incident Report 96-055; however, the licensee failed to determine the cause of this condition and failed to take corrective actions to preclude repetition.
5.
In March 1997, information was received from a motor-operated valves analysis and test system by Technical Notice MUTN 96-02 that previously provided error information related to the 3500 diagnostic system strain modules was nonconservative; however, an ooeration, notification, and evaluation form was not initiated to evaluate the occurrence.
This is a Severity Level IV violation (Supplement 1)(50-445;-446/9712-01).
]
C.
10 CFR 50.59(a)(1) states, ".. the holder of a license authorizing operation of a j
production utilization facility may (i) make changes in the facility as described in the safety analysis report... unless the proposed change... involves... an unreviewed safety question."
4 10 CFR 50.59(b)(1) states, "... the licensee shall maintain records of changes in the facility... to the extent that these changes constitute changes in the facility as described in the safety analysis report... These records must include a written 1
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