ML16127A312
| ML16127A312 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/14/1989 |
| From: | Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML16127A311 | List: |
| References | |
| 50-269-89-05, 50-269-89-5, 50-270-89-05, 50-270-89-5, 50-287-89-05, 50-287-89-5, NUDOCS 8904030316 | |
| Download: ML16127A312 (4) | |
Text
.41 ENCLOSURE 1 NOTICE OF VIOLATION Duke Power Company Docket No. 50-269, 270, 287 Oconee Units 1, 2 and 3 License No. DPR-38, 47, 55 During the Nuclear Regulatory Commission (NRC) inspection conducted January 17 February 17,
- 1989, two violations of NRC requirements were identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR, Part 2, Appendix C (1988),
the violations are listed below:
A.
Oconee Nuclear Station Technical Specification (TS) 6.4.1 states that the station shall be operated and maintained in accordance with approved procedures and that these procedures shall contain appropriate check-off lists and instructions.
The Oconee Nuclear Station Emergency Operating Procedure (EP/1/A/1800/01) contains procedures to be used to place and' maintain the reactor in a safe condition following certain events.
Contrary to the above, portions of the procedures concerning actions to be taken by the operators were inadequate, in that -guidance was insufficient in the areas of the Thermal Shock Operating Range (TSOR) and use of Auxiliary Pressurizer Spray as indicated in the following examples:
- 1. Management was uncertain whether existing plant conditions required entry into the TSOR.
Analysis after the event indicates that the TSOR should have been entered.
- 2. Auxiliary Pressurizer Spray was initiated with a differential temperature (spray-pressurizer) in excess of the 410 degrees F which resulted in a violation of TS 3.1.2.6.
- 3. Management was reluctant to utilize the Power Operated Relief Valve (PORV) to reduce pressure to the TSOR, consequently the TSOR was not entered. The EOP does not specify how to reduce pressure to get into the TSOR, only to do so.
Additionally the guidance does not specify how time sensitive entry into the TSOR is.
This is a Severity Level IV violation (Supplement 1).
B. Oconee Nuclear Station Technical Specification 6.4.1 states that the station shall be operated and maintained in accordance with approved procedures.
Oconee Nuclear Station Directive 2.2.2 "Independent Verification" and Directive 3.2.1 "Work Request" contain specific procedures to be followed to accomplish Independent Verification and Correct Component Verification during work.
8904030316 890314 PDR ADOCK 05000269 PNU
Duke Power Company 2
Docket No. 50-269, 270, 287 Oconee Units 1, 2 and 3 License No. DPR-38, 47, 55 Contrary to the above, due to programmatic weaknesses in the training and qualification of Construction and Maintenance Division (CMD) workers performing Nuclear Station Modification (NSM) work, these procedures were not followed.
The below listed incidents are examples resulting from these weaknesses in the training and qualification areas:
- 1. The cutting of an incorrect pipe in the Unit One High Pressure Injection Pump room.
- 2. A Unit 2 reactor trip due to an improperly installed wire which caused a ground on the 125VDC system.
This is a Severity Level IV violation (Supplement 1).
Pursuant to the provisions of 10 CFR 2.201, Duke Power Company is hereby required to submit a written statement or explanation to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D. C. 20555, with a copy to the Regional Administrator, Region II, and. a copy to the NRC Resident Inspector, Oconee, within 30 days of the date of the letter transmitting thi's Notice.
This reply should be clearly marked as a "Reply to a Notice of Violation" and should include:
(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 will be given to extending the response time.
If an adequate reply is not received within the time specified in this Notice, a order may be issued to show cause why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken.
FOR THE NUCLEAR REGULATORY COMMISSION Alan R. Herdt, Chief Reactor Projects Branch 3 Division of Reactor Projects Dated at Atlanta, Georgia this i.Ls day of March 1989
ENCLOSURE 1 NOTICE OF VIOLATION Duke Power Company Docket No. 50-269, 270, 287 Oconee Units 1, 2 and 3 License No. DPR-38, 47, 55 During the Nuclear Regulatory Commission (NRC) inspection conducted January 17 February 17,
- 1989, two violations of NRC requirements were identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR, Part 2, Appendix C (1988),
the violations are listed below:
A.
Oconee Nuclear Station Technical Specification (TS) 6.4.1 states that the station shall be operated and maintained in accordance with approved procedures and that these procedures shall contain appropriate check-off lists and instructions.
The Oconee Nuclear Station Emergency Operating Procedure (EP/1/A/1800/01) contains procedures to be used to place and maintain the reactor in a safe condition following certain events.
Contrary to the above, portions of the procedures concerning actions to be taken by the operators were inadequate, in that guidance was insufficient in the areas of the Thermal Shock Operating Range (TSOR) and use of Auxiliary Pressurizer Spray as indicated in the following examples:
- 1. Management was uncertain whether existing plant conditions required entry into the TSOR.
Analysis after the event indicates that the TSOR should have been entered.
- 2. Auxiliary Pressurizer Spray was initiated with a differential temperature (spray-pressurizer) in excess of the 410 degrees F which resulted in a violation of TS 3.1.2.6.
- 3. Management was reluctant to utilize the Power Operated Relief Valve (PORV) to reduce pressure to the TSOR, consequently the TSOR was not entered.
The EOP does not specify how to reduce pressure to get into the TSOR, only to do so.
Additionally the guidance does not specify how time sensitive entry into the TSOR is.
This is a Severity Level IV violation (Supplement 1).
B. Oconee Nuclear Station Technical Specification 6.4.1 states that the station shall be operated and maintained in accordance with approved procedures.
Oconee Nuclear Station Directive 2.2.2 "Independent Verification" and Directive 3.2.1 "Work Request" contain specific procedures to be followed to accomplish Independent Verification and Correct Component Verification during work.
Duke Power Company 2
Docket No. 50-269, 270, 287 Oconee Units 1, 2 and 3 License No. DPR-38, 47, 55 Contrary to the above, due to programmatic weaknesses in the training and qualification of Construction and Maintenance Division (CMD) workers performing Nuclear Station Modification (NSM) work, these procedures were not followed.
The below listed incidents are examples resulting from these weaknesses in the training and qualification areas:
- 1. The cutting of an incorrect pipe in the Unit One High Pressure Injection Pump room.
- 2. A Unit 2 reactor trip due to an improperly installed wire which caused a ground on the 125VDC system.
This is a Severity Level IV violation (Supplement 1).
Pursuant to the provisions of 10 CFR 2.201, Duke Power Company is hereby required to submit a written statement or explanation to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D. C. 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, Oconee, within 30 days of the date of the letter transmitting this Notice.
This reply should be clearly marked as a "Reply to a Notice of Violation" and should include:
(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 will be given to extending the response time.
If an adequate reply is not received within the time specified in this Notice, a order may be issued to show cause why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken.
FOR HE NUCLEAR REGULATORY COMMISSION Alan R. Herdt, Chief Reactor Projects Branch 3 Division of Reactor Projects Dated at Atlanta, Georgia this ilqIday of March 1989