ML20153F516

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Notice of Violation from Insp on 880319-0422.Violation Noted:Procedure PT/O/A/4150/05 Not Properly Implemented & Procedure PT/2/A/4200/28A Not Properly Maintained
ML20153F516
Person / Time
Site: Mcguire, McGuire  Duke energy icon.png
Issue date: 04/29/1988
From: Brownlee V
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20153F513 List:
References
50-369-88-09, 50-369-88-9, 50-370-88-09, 50-370-88-9, NUDOCS 8805100355
Download: ML20153F516 (4)
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. O ENCLOSURE 1 E2TICE OF VIOLATION Duke Power Company Docket Nos. 50-369, 370 McGuire Units 1 and 2 License Nos. NPF-9, NPF-17 During the Nuclear Regulatory Commission (NRC) inspection conducted on March 19, 1988 through April 22, 1988, 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 (1987), the violations are identified below:

A. Technical Specification (TS) 6.8.1.a. requires that written procedures be established, implemented, and maintained covering the activities delineated in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978. Regulatory Guide 1.33, Revision 2, February 1978, Appendix A, requires, in ;; art, that surveillanca procedures be written and implemented for testing including pressurizer safety valve tests and reactor protection system tests.

McGuire procedure PT/0/A/4150/05, Pressurizer Safety Valve Setpoint Test, requires that each of three lifts of the valve be with in the TS required band at 2483 psig plus or minus one percent (2461 to 2509 psig).

1. Contrary to the above, procedure PT/0/A/4150/05 was not properly implemented in that the second lift of 2NC1 on June 11, 1987, was outside of the required band (4 psi high) and the test was signed off as satisfactory by both maintenance and quality control personnel.
2. Contrary to the above, procedure PT/2/A/4200/28A, Slave Relay Testing, was not properly maintained in that an error in the procedure caused Unit 2 non-safety containment ventilation systems to inadvertently re-align to alternate power sources on March 22, 1988.

This is a Severity Level IV violation (Supplement I) and is applicable to Unit 2 only.

8. Technical Specification (TS) 3.7.3 requires that, in Modes 1-4, two independent Component Cooling Water (KC) System loops be operable. With only one KC loop operable, both loops must be returned to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or the unit must be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Contrary to the above, Ur.it I was operated in Mode 1 for greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with KC loop 8 inoperable between January 29, 1988 and March 9, 1988. KC loop B was inoperable in that the Nuclear Service Water (RN) throttle valve to KC heat exchanger 1B (RN-1908), would not have positioned to provide full design RN flow to the heat exchanger if required to do so in an engineered safety features actuation.

8805100355 PDR 880429 Q ADOCK 05000369 DCD

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Duke Power Company 2 Docket Nos. 50-369, L'70 McGuire Units 1 and 2 License Nos. NPF-9, NFF-17 This is a Severity Level IV violation (Supplement I) and is applicable to Unit 1 only.

C. Technical Specification (TS) 4.0.5 requires th ; inservice testing of ASME Code Class 1, 2, and 3 valves be performed in accordance with Section XI of the ASME Boiler and Pressure Vessei Code.

Article IWV 3200 of Section XI of the ASME Boiler and Pressure Vessel Cade requires that valves which perform a specific function in shutting down a reactor to the cold shutdown condition or in mitigating the consequences of an accident shall be tested, following maintenance, and prior to the time of being returned to service, to demonstrate that the performance parameters which could be affected by the maintenance are within acceptable limits.

Contrary to the above, Unit 1 Nuclear Service Water (RN) valve RN-21 underwent maintenance in the form of a packing adjustment on February 4, 1988 but did not receive a valve stroke timing test to verify valve shutting time to be within required limits.

This is a Severity Level IV violation (Supplement I) and is applicable to Unit 1 only.

Pursuant to the provisions of 10 CFR 2.201, Duke Power Company is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washingten, DC 20555 with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, McGuire Nuclear Station 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 for each violation: (1) the reason for the violation if admitted (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.

Where good cause is shown, consideration will be given to extending the response time. If an adaquate reply is not received within the time specified in this Notice, an 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 ORIGINAL SIGtna gy VIRGIL L. L'.lCWNLEE Virgil L. Brownlee, Chief Reactor Projects Branch 3 Division of Reactor Projects CatedagAtlanta, Georgia this // day of April 1988

e ENCLOSURE 1 NOTICE OF VIOLATION Duke Power Company Docket Nos. 50-369, 370 McGuire Units 1 and 2 License Nos. NPF-9, NPF-17 During the Nuclear Regulatory Commission (NRC) inspection conducted on March 19, 1988 through April 22, 1988, 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 (1987), the violations are identified below:

A. Technical Specification (TS) 6.8.1.a. requires that written procedures be ,

established, implemented, and maintained covering the activities delineated in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978. Regulatory Guide 1.33, Revision 2, February 1978, Appendix A, requires, in part, that surveillance procedures be written and implemented for testing including pressurizer safety valve tests and reactor protection system tests.

McGuire procedure PT/0/A/4150/05, Pressurizer Safety Valve Setpoint Test, requires that each of three lifts of the valve be with in the TS required band of 2485 psig plus or minus one percent (2461 to 2509 psig).

1. Contrary to the above, procedure PT/0/A/4150/05 was not properly implemented in that the second lift of 2NC1 on June 11, 1987, was outside of the required band (4 psi high) and the test was signed off as satisfactory by both maintenance and quality control personnel.
2. Contrary to the above, procedure PT/2/A/4200/28A, Slave Relay Testing, was not properly maintained in that an error in the procedure caused Unit 2 non-safety containment ventilation systems to inadvertently re-align to alternate power sourc.es on March 22,  ;

1938.

This is a Severity Level IV violation (Supplement I) and is applicable to Unit 2 only.

B. Technical Specification (TS) 3.7.3 requires that, in Modes 1-4, two independent Component Cooling Water (KC) System loops be operable. With only one KC loop operable, both loops must be returned to operable status  ;

within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or the unit must be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. I Contrary to the above, Unit I was operated in Mode 1 for greater than 72 j hours with KC loop B inoperable between January 29, 1988 and March 0, 1988. KC loop B was inoperable in that the Nuclear Service Water (RN) throttle valve to KC heat exchanger IB (RN-1908), would not have positioned to provide full design RN flow to the heat exchanger if required to do so in an engineered safety features actuation.

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Duke Power Company 2 Docket Nos. 50-369, 370 McGuire Units 1 and 2 License Nos. NPF-9, NPF-17 This is a Severity Level IV violation (Supplement I) and is applicable to Unit 1 only. ,

C. Technical Specification (TS) 4.0.5 requires that inservice testing of ASME Code Class 1, 2, and 3 valves be perforced in accordance with Section XI of the ASME Boiler and Pressure Vessel Code.

Article IWV 3200 of Section XI of the ASME Boiler and Pressure Vessel Code requires that valves which perform a specific function in shutting down a  :

reactor to the cold shutdown condition or in mitigating the consequences of an accident shall be tested, following maintenance, and prior to the time of being returned to service, to demonstrate that the performance parameters which could be affected by the maintenance are within acceptable limits.

Contrary to the above, Unit 1 Nuclear Service Water (RN) valve RN-21 underwent maintenance in the form of a packing adjustment on February 4, 1988 but did not receive a valve stroke timing test to verify valve shutting time to be within required limits.

This is a Severity Level IV violation (Supplement I) and is applicable to  !

Unit 1 only.

Pursuant to the provisions of 10 CFR 2.201, Duke Power Company is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555 with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, McGuire Nuclear Station 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 for each violation: (1) the reason for the violation if admitted, (2) the corrective steps that have been taken and  ;

the results achievt/ (3) the corrective steps that will be taken to avoid  !

further violations, and (4) the date wher 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 l in this Notice, an 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 *,aken.

FOR THE NUCLEAR REGULATORY COMMISSION l

VI'rg i j nLA

. Brownlee, Chief l Reactor Projects Branch 3 i Division of Reactor Projects  ;

I Dated at Atlanta, Georgia this g day of April 1983 J

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