ML20198N207
| ML20198N207 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 01/14/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20198N193 | List: |
| References | |
| 50-445-97-15-01, 50-445-97-15-1, 50-446-97-15, NUDOCS 9801200292 | |
| Download: ML20198N207 (2) | |
Text
I i
plCLOSURE NOTICE OF VIOLATION TU Electric Docket Nos.:
50-445 Comanche Pe4 Steam Electric Station 50 446 License Nos.:
NPF 87 NPF 89 During an NRC inspection conducted on June 8 through July 19, and subsequent loothee reviews which concluded on November 14,1997, one violation of NRC requirements was identified, in accordance with the
- General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG 1600, the violation is listed below:
A.
10 CFR Part 50, Appendix B, Criterion V, requires in part, that procedures include appropriate quantitative acceptance criteria for determining that important activities havo been satisf actorily accomplished.
Operations Testing Manual Procedures OPT 102A, Revision a for Unit 1, and OPT 102B, Revision 2 for Unit 2, " Operations Shiftly Routine Tests," implemented Technical Specification Surveillance Requirement 4.7.10 fur area temperature monitoring of the main steam and feedwater penetration areas by using Temperature Indicators 1 TI 5624 and 2 TI 5624 to assure that the Technical Specification 3/4.7.10 temperature limit of 104'F is not exceeded for more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Test data taken to resolve Operations Notification and Evaluation Form 97 790 showed that the averaged bulk area temperatures of the main steam and feedwater i
penetration areas differed from Temperature Indicators 1 TI 5624 or 2 TI 5624 by up to
- 1.1 *F.
Contrary to the above, Procedures OPT-102A and OPT-1028 did not include appropriate quantitative acceptance criteria in that they failed to account for the difference between the averaged bulk area temperatures of the main steam and feedwater penetration areas and Temperature Indicators 1 TI 5624 or 2 TI 5624 in the acceptance criteria.
This is a Severity Level IV violation (Supplement 1) (50 445(446)/9715 03).
The NRC has concluded that information regarding the leason for the violation, corrective actions taken, plans to correct the violation and prevent recurrence, and the date when full compliance will be achieved is already adequately addressed on the docket in your letters
- dated October 3 and 15,1997. However, you are required to submit a written statement or explanation pursuant to 10 CFR 2.201 if the description therein does not accurately reflect your corrective actions or position, if you choose to respond, clearly mark your response at a Raply to a Notice of Violation," and send it to the U.S. Nuclear Reguletory Commission, ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the l
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~ Regional Administrator, Region IV, and a copy to the NRC Resident inspector at the facility
-that 1 t e su ect o tf his Notice, within 30 days of the date of the letter transmitting this 1 h bj Notice of Violation.
l Dated at Arlington, Texas this 14 day of January, Ifr98 i
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