ML17306A673
| ML17306A673 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 04/07/1992 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17306A672 | List: |
| References | |
| 50-528-92-05, 50-528-92-5, 50-529-92-05, 50-529-92-5, 50-530-92-05, 50-530-92-5, NUDOCS 9204220047 | |
| Download: ML17306A673 (4) | |
Text
NOTICE OF VIOLATION Arizona Public Service Co.
Palo Verde Units 1, 2, and 3
Docket No. 50-528, 50-529, and 50-530 License No. NPF-41, NPF-51, and NPF-74 During 'an NRC inspection conducted on January 26 through February 29,
- 1992, three violations of NRC requirements were identified.
In accordance with the "General Statement.of Policy and Procedure for NRC Enforcement Action," 10,CFR Part 2, Appendix C, the violations are listed below:
A.
Unit 1 Technical Specification 6.8.1 states, in part, that written procedures shall be established, implemented, and maintained covering the activities recommended in Appendix A of Regulatory Guide 1.33; Revision 2, February, 1978.
Regulatory Guide 1.33, Revision 2, Appendix A, recommends surveillance procedures and general plant operating procedures.
1.
Surveillance procedure 36ST-9SB02, "PPS Bistable Trip Units Functional Test," Step 8. 11.6.2, requires the test performer to "ensure LO SG2 PRESS Trip Setpoint (Parameter
- 12) is at the MAXIMUM VALUE when in Mode 1 or 2.
Adjust as necessary."
Contrary to the above, on February 4,
- 1992, when performing step
- 8. 11.6.2, the test performer failed to ensure the LO SG2 PRESS trip setpoint (parameter
- 12) was at the maximum value when the unit was in Mode 1, resulting in the setpoint being approximately 50 pounds per square inch less that the minimum value allowed by Technical Specifications 2.2.1 and 3.3.2.
2.
General operating procedure 40DP-90P05, "Control Room Data Sheet Instructions,"
Step 2.3.2, requires that a reactor operator report "any abnormal and/or unusual condition" while filling out the Control Room Data Sheets.
Contrary to the above, on February 4, 1992, at 5:00 pm, while filling out the Control Room Data Sheets, the reactor operator failed to note that the f2 steam generator low pressure setpoint was incorrectly set.
This is a Severity Level IV violation (Supplement I) applicable to Unit 1.
B.
Unit 1 Technical Specification 6.8. 1 states, in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures, recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
I Regulatory Guide 1.33, Appendix A, recommends procedures for performing maintenance and states that maintenance that can affect the performance of safety-related equipment should be properly preplanned and performed 9204220047 920407 PDR ADOCK 05000528
'8 PDR
in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances.
Licensee Procedure 36MT-9RI06, "Withdrawal of ICI Cables,"
Section 8.4.5, requires the control element assembly (CEA) hoist to be used when withdrawing fixed incore instruments (ICIs) for refueling operations.
Contrary to the above, on February 25, 1992, the licensee failed to implement Procedure 36MT-9RI06, in that fixed ICI f55 was manually withdrawn without using the CEA hoist.
This is a Severity Level IV violation (Supplement I) applicable to Unit. 1.
C.
10 CFR 50, Appendix B, Criterion XII, requires that measures be established to assure that tools,
- gages, instruments, and other measuring and testing devices used in activities affecting quality are properly controlled, calibrated, and.adjusted at specified periods to maintain accuracy within necessary limits.
Contrary to the above, no measures were established to assure that calibration gas used for performance of containment hydrogen monitor surveillance tests, an activity affecting quality, was properly controlled and calibrated.
Specifically, on February 11, 1992, the Unit 2 Containment Hydrogen Monitor Channel A surveillance test (Procedure 36ST-9HP03) was performed using a calibration gas that was not procured from a gA approved vendor and no other gA controls were provided to assure the proper calibration of the gas.
On February 13,
- 1992, one containment hydrogen monitor. each in Units 1 and 3, were also determined to have had surveillance tests performed with calibration gas that was not properly controlled or calibrated.
This is a Severity Level IV violation (Supplement
- 1) applicable to Units 1, 2
and 3.
Pursuant to the provisions of 10 CFR 2.201, Arizona Public Service Company is hereby required to submit a written statement or explanation to the U. S.
Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, D.C.
20555 with a copy to the Regional Administrator, Region V, and a copy to the NRC Resident Inspector at the facility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice).
This reply should be clearly marked as a "Reply to a Notice of Violation" and should include for each violation:
(1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results
- achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.
If an adequate reply is not received within the time specified in this Notice, the Commisision may issue
~
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an order or a demand for information as to why.the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken.
Where good cause is shown, consideration will be given
.to extending the response time.
Dated at Walnut Creek, California this ~N day of ~A~:,
1992