05000416/FIN-2015004-05

Finding

Title

Licensee-Identified Violation

Description

Technical Specification 3.6.1.3, Surveillance Requirement 3.6.1.3.9, requires, verification of combined leakage rate of 1 gallon per minute times the total number of primary containment isolation valves through hydrostatically tested lines that penetrate the primary containment is not exceeded when these isolation valves are tested at greater than or equal to 1.1 times peak containment pressure. Contrary to the above, since June 6, 2012, the licensee failed to verify combined leakage rate of 1 gallon per minute times the total number of primary containment isolation valves through hydrostatically tested lines that penetrate the primary containment is not exceeded when these isolation valves are tested at greater than or equal to 1.1 times peak containment pressure. Specifically, the post-extended power uprate peak containment pressure analyzed increased to 14.8 psig, resulting in a new required test pressure of 16.28 psig. The licensee did not test primary containment isolation valves 1P11F130 and 1P11F131 using the new higher pressure. The licensee subsequently declared the valves inoperable and tested the two valves using the new peak containment pressure. The valves passed the surveillance test and were declared operable at 11:01 am on October 15, 2015. This finding was entered in the licensee's corrective action program as Condition Report CR-GGN-2015-05072. The finding is more than minor because it was associated with the barrier performance attribute of the Barrier Integrity Cornerstone and adversely affected the cornerstone objective to provide reasonable assurance that physical design barriers (containment) protect the public from radionuclide releases caused by accidents or events. Specifically, the licensee never performed Technical Specification Surveillance Requirement 3.6.1.3.9, and therefore did not have presumption of operability to provide the reasonable assurance that containment would protect the public from radionuclide releases caused by accidents or events. The significance of the finding was assessed using Inspection Manual Chapter 0609, Appendix A, Exhibit 3, Barrier Integrity Screening Questions, and it was determined to be of very low safety significance (Green).

05
Site:	Grand Gulf
Report	IR 05000416/2015004 Section 4OA7
Date counted	Dec 31, 2015 (2015Q4)
Type:	NCV: Green
cornerstone	Mitigating Systems
Identified by:	Licensee-identified
Inspection Procedure:
Inspectors (proximate)	D Loveless E Simpson G Guerra G Pick G Warnick H Freeman J Buchanan M Phalen M Young N Day N Greene
Violation of:	Technical Specification
INPO aspect
'
v • d • e

Finding - Grand Gulf - IR 05000416/2015004

1(6)2(5)3(1)4(6)5(0)6(0)7(11)8(4)201(6)301(1)402(0)403(0)404(3)405(4)406(1)501(0)

IR 05000416/2015004: 1 2 3 4 5 6

Finding List (Grand Gulf) @ 2015Q4

CCA Matrix: 2015Q4

	Q	CCA	Title
05000416/FIN-2015001-02	2015Q1	H.12	Failure to Follow a Procedure Resulting in the Unplanned Inoperability of the Reactor Core Isolation Cooling System
05000416/FIN-2015001-05	2015Q1	H.8	Failure to Establish, Implement, and Maintain Appropriate Changes to the Offsite Dose Calculation Manual For REMP Airborne Sampling
05000416/FIN-2015001-04	2015Q1	H.1	Failure to Properly Calibrate Main Steam Line Radiation Monitors and Containment/Drywall High Range Radiation Monitors
05000416/FIN-2015001-03	2015Q1	P.2	Emergency Action Level Scheme for Nonfunctional Seismic Monitor
05000416/FIN-2015201-06	2015Q1		Security
05000416/FIN-2015201-05	2015Q1		Security
05000416/FIN-2015201-04	2015Q1		Security
05000416/FIN-2015201-03	2015Q1		Security
05000416/FIN-2015201-02	2015Q1		Security
05000416/FIN-2015201-01	2015Q1		Security
05000416/FIN-2015001-01	2015Q1		Failure to Take Timely Corrective Actions Associated with Division 1 and 2 Standby Service Water Pump House Ventilation System Due to Degraded Relays
05000416/FIN-2015001-06	2015Q1		Failure to Adequately Establish Commercial-Grade Items as Basic Components
05000416/FIN-2015002-03	2015Q2		Failure to the Update the Final Safety Analysis Report after the Extended Power Uprate
05000416/FIN-2015002-04	2015Q2		Possible Loss of Communications Systems during Control Room Fire Scenarios
05000416/FIN-2015002-01	2015Q2	H.12	Failure to Have Appropriate Instructions Resulted in the Unplanned Unavailability of the Reactor Core Isolation Cooling System
05000416/FIN-2015002-02	2015Q2	H.12	Failure to Identify High Vibration on the Division 3 EDG Soak Back Oil Pump
05000416/FIN-2015405-01	2015Q3		Security
05000416/FIN-2015003-01	2015Q3		Failure to Have Appropriate Instructions for Preventative Maintenance on the Division II Diesel Generator Fuel Rack Control Lever
05000416/FIN-2015007-05	2015Q4		Failure to Maintain a Safety-Related Cable Tray Overfill Analysis Record
05000416/FIN-2015007-02	2015Q4	H.6	Failure to Ensure that Electrical Interrupting Devices are Rated for Available Fault Current Levels
05000416/FIN-2015004-03	2015Q4		Failure to Make a Required Eight-Hour Report for Loss of Safety Function
05000416/FIN-2015007-07	2015Q4		Failure to Update the Final Safety Analysis Report
05000416/FIN-2015008-03	2015Q4	H.12	Failure to Declare Secondary Containment Inoperable Based on Failed Surveillance Testing
05000416/FIN-2015404-03	2015Q4		Security
05000416/FIN-2015404-02	2015Q4		Security
05000416/FIN-2015404-01	2015Q4		Security
05000416/FIN-2015007-08	2015Q4		Incomplete and Inaccurate Response to NRC Bulletin 88-04
05000416/FIN-2015008-04	2015Q4		Failure to Make Required Event Notification
05000416/FIN-2015007-03	2015Q4	S.4(o)	Lack of Coordination of Division III HPCS Switchgear 127N Undervoltage Relays
05000416/FIN-2015007-01	2015Q4		Failure to Ensure Safety-Related Alternating Current and Direct Current Equipment Operability and Functionality at Maximum Allowable Voltage Levels
05000416/FIN-2015008-01	2015Q4	P.1	Failure to Enter a Condition Adverse to Quality into the Corrective Action Program
05000416/FIN-2015007-04	2015Q4	H.8	Failure to Identify and Address Impacts of Revised Calculation Output Data
05000416/FIN-2015007-06	2015Q4		Failure to Perform Surveillance Requirement 3.8.1.9
05000416/FIN-2015007-09	2015Q4		Failure to Obtain a License Amendment for Use of Probabilistic Methods to Evaluate Tornado Missile Hazards
05000416/FIN-2015007-10	2015Q4	P.6	Failure to Ensure Equipment Operability and Functionality of Allowable Alternating Current Frequency Range
05000416/FIN-2015007-11	2015Q4	H.12	Failure to Implement Equipment Control Procedures for Loose Items in Containment
05000416/FIN-2015004-04	2015Q4		Failure to Establish Adequate Maintenance Instructions to Perform Work Activities on the Division III Diesel Generator Overspeed Trip Limit Switch
05000416/FIN-2015004-02	2015Q4	H.14	Failure to Timely Enter Technical Specification Surveillance Requirement 3.0.1
05000416/FIN-2015004-01	2015Q4	H.6	Failure to Have Appropriate Instructions for Preventative Maintenance on the Division I Diesel Generator Simulated Run
05000416/FIN-2015301-01	2015Q4	H.8	Inadequate Plant Operating Procedures with Eight Examples
05000416/FIN-2015008-02	2015Q4	P.1	Failure to Promptly Initiate Condition Reports

Self-Identified List (Grand Gulf)

	Q	Title
05000416/FIN-2015002-05	2015Q2	Licensee-Identified Violation
05000416/FIN-2015405-02	2015Q3	Licensee-Identified Violation
05000416/FIN-2015405-03	2015Q3	Licensee-Identified Violation
05000416/FIN-2015405-04	2015Q3	Licensee-Identified Violation
05000416/FIN-2015406-01	2015Q3	Security
05000416/FIN-2015004-05	2015Q4	Licensee-Identified Violation
05000416/FIN-2015004-06	2015Q4	Licensee-Identified Violation

[Grand Gulf Findings full list]

05000416/FIN-2015004-05

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