05000323/LER-2012-002, Regarding Coupling Capacitor Voltage Transformer Bushing Failure Causes Reactor Trip

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Regarding Coupling Capacitor Voltage Transformer Bushing Failure Causes Reactor Trip
ML12346A266
Person / Time
Site: Diablo Canyon Pacific Gas & Electric icon.png
Issue date: 12/10/2012
From: Allen B
Pacific Gas & Electric Co
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
DCL-12-127 LER 12-002-00
Download: ML12346A266 (9)


LER-2012-002, Regarding Coupling Capacitor Voltage Transformer Bushing Failure Causes Reactor Trip
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(iv)(A), System Actuation

10 CFR 50.73(a)(2)(i)

10 CFR 50.73(a)(2)(vii), Common Cause Inoperability

10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded

10 CFR 50.73(a)(2)(viii)(A)

10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition

10 CFR 50.73(a)(2)(viii)(B)

10 CFR 50.73(a)(2)(ix)(A)

10 CFR 50.73(a)(2)(x)

10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor

10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat

10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown

10 CFR 50.73(a)(2)(v), Loss of Safety Function

10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
3232012002R00 - NRC Website

text

Pacific Gas and Electric Company December 10, 2012 PG&E Letter DCL-12-127 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-323, OL-DPR-82 Diablo Canyon Unit 2 Barry S. Allen Site Vice President 10 CFR 50.73 Diablo Canyon Power Plant Mail Code 104/6 P. O. Box 56 Avila Beach, CA 93424 805.545.4888 Internal: 691.4888 Fax: 805.545.6445 Licensee Event Report 2-2012-002-00, Coupling Capacitor Voltage Transformer Bushing Failure Causes Reactor Trip

Dear Commissioners and Staff:

Pacific Gas and Electric Company (PG&E) is submitting the enclosed Licensee Event Report (LER) identifying reactor trip and an auxiliary feedwater pump auto-start as a result of a flashover of a 500kV insulator. PG&E is submitting this LER in accordance with 10 CFR 50.73(a)(2)(iv)(A).

PG&E makes no new or revised regulatory commitments (as defined by NEI 99-04) in this report.

This event did not adversely affect the health and safety of the public.

Sincerely,

~~,-

Barry S. Allen ssz1 14040/50518473 Enclosure cc/enc:

Elmo E. Collins, NRC Region IV Thomas R. Hipschman, NRC Senior Resident Inspector Joseph M. Sebrosky, NRR Senior Project Manager INPO Diablo Distribution A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

  • Comanche Peak
  • Diablo Canyon
  • Palo Verde
  • San Onofre
  • Wolf Creek

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150*0104 EXPIRES: 10/31/2013 (10*2010)

, the NRC may digits/characters for each block) not conduct or sponsor, and a person is not required to respond to, the information collection.

I3.PAG~

Diablo Canyon Power Plant, Unit 2 05000-323 OF 8

4. TITLE Coupling Capacitor Voltage Transformer Bushing Failure Causes Reactor Trip
5. EVENT DATE
6. LER NUMBER
7. REPORT DATE
8. OTHER FACILITIES INVOLVED YEAR 1 SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR NUMBER NO.

MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 10 11 2012 2012 - 002. 00 12 10 2012

9. OPERATING MODE
11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) o 20.2201 (b) o 20.2203(a)(3)(i) o 50.73(a)(2)(i)(C) o 50.73(a)(2)(vii) 1 o 20.2201(d) o 20.2203(a)(3)(ii) o 50.73(a)(2)(ii)(A) o 50.73(a)(2)(viii)(A) o 20.2203(a)(1) o 20.2203(a)(4) o 50.73(a)(2)(ii)(B) o 50.73(a)(2)(viii)(B) o 20.2203(a)(2)(i) o 50.36(c)(1)(i)(A) o 50. 73(a)(2)(iii) o 50.73(a)(2)(ix)(A)
10. POWER LEVEL o 20.2203(a)(2)(ii) o 50.36(c)(1)(ii)(A) o 50.73(a)(2)(iv)(A) o 50.73(a)(2)(x) o 20.2203(a)(2)(iii)

B 50.36(c)(2) o 50.73(a)(2)(v)(A) o 73.71(a)(4) 100 o 20.2203(a)(2)(iv) 50.46(a)(3)(ii) o 50.73(a)(2)(v)(B) o 73.71(a)(5) o 20.2203(a)(2)(v) o 50.73(a)(2)(i)(A) o 50.73(a)(2)(v)(C) o OTHER o 20.2203(a)(2)(vi) o 50.73(a)(2)(i)(B) o 50.73(a)(2)(v)(D)

Specify in Abstract below or in Creepage distance is the shortest path between two conductive parts. The Institute of Electrical and Electronics Engineers (IEEE) standard C57.19.100, "IEEE Guide for Application of Power Apparatus Bushings," provides recommendations for various environmental conditions. DCPP's location exposes these systems and components to environmental contaminants such as salt, dust, industrial pollutants, etc. Per IEEE C57.19.100, DCPP's environment is classified as a heavy or very heavy contamination area, which establishes the recommended minimum creepage distance as 502 or 616 inches, respectively. PG&E's corporate transmission line design standard indicates a minimum creepage distance of 400 inches, but does not refer to environmental classifications.

The installed polymer CCVT's have a vendor stated guaranteed minimum of 400 inches of creepage distance. The previous porcelain CCVT's had a specified creepage distance of 435 inches per vendor documents; it was actually found to be 521 inches.

Relative to the auxiliary feedwater pump, PG&E had implemented a temporary setpoint change in March 2012 to address a deficiency related to Rosemount transmitter uncertainty error increase. This resulted in a setpoint change for each ofthe steam generator (SG) low-low level setpoints from 15 percent to 17 percent for the auxiliary feedwater (AFW) pump autostarts. Procedures were reviewed to identify necessary changes due to the level setpoint changes, particularly reviewing all 15 percent level values in the procedures to implement necessary changes.

The Emergency Operating Procedure EOP E-O.1, "Reactor Trip Response," Response Not Obtained, Step 6.c, checks whether the turbine-driven (TD) AFW pump should be secured by verifying SG level greater than 16 percent in at least 3 SG's. The 16 percent value is derivative of the 15 percent AFW start setpoint, but is not

.explained as such in the setpoint basis documents or in the text of the procedures. Without a clear link between the 15 percent and the 16 percent value provided in the procedure or setpoint bases documents, procedure writers failed to identify the need to increase the 16 percent procedure requirement.

B. Event Description

On October 11,2012, during a light rain, plant personnel identified visible arcing on the Unit 2 "A" and "B" Phase MBT CCVT's. At 1208 PDT, the "A" Phase MBT CCVT flashed over to ground, causing a single-line-to-ground fault. This caused the 500kV tie-line differential relay to actuate, resulting in a Unit 2 trip. The Unit 2 trip actuated a turbine trip and, because Unit 2 was operating above the 50 percent power permissive, the reactor protection system initiated a Unit 2 reactor trip. All plant equipment, including the auto start of the AFW system, responded as designed.

About 18 minutes after the reactor trip, plant operators manually closed the steam supply valve to the TD AFW pump to secure the pump. Operators performed this action in accordance with plant operating procedures after they verified that the indicated SG levels were greater than the procedural requirement of 16 percent narrow range span. However, because the SG low-level bistables associated with the AFW actuation circuits had not yet cleared, the emergency safeguards actuation signal drove the steam-supply valve back open, restarting the TD AFW pump. Operators increased steam generator levels to clear the bistables and successfully reclosed the steam-supply valve.

YEAR I SEQUENTIAL T NUMBER I 2012 -

002 REV NO.

00 C. Status of Inoperable Structure, Systems, or Components That Contributed to the Event None.

D. Other Systems or Secondary Functions Affected

None.

E. Method of Discovery

4 Annunciators in the control room alerted licensed control room operators of the 500kV system problem.

F. Operator Actions

Plant operators verified appropriate plant trip response using Emergency Operating Procedure (EOP) E-O, "Reactor Trip or Safety Injection" and EOP E-O.l, "Reactor Trip Response."

G. Safety System Responses Vital buses transferred from auxiliary power to startup power as designed.

III. Cause of the Problem A. Immediate Cause OF 8

Inadequate material performance of the silicone polymer insulator prevented proper control of environmental contamination. Furthermore, the insulator design criteria, including creepage distance and operating environment assumptions, were not sufficiently conservative.

B. Root Cause PG&E identified the following root causes:

(1) PG&E found that inappropriate material performance of the silicone polymer insulator prevented proper control of environmental contamination. Detailed material testing of the failed CCVT bushing is ongoing and a supplement to this Licensee Event Report will be submitted following receipt of this report to address any additional findings.

YEAR

6. LER NUMBER I

SEQUENTIAL I NUMBER 2012 -

002 REV NO.

00 5

3. PAGE OF (2) PG&E concluded that engineers violated INPO 10-005, "Principles for Maintaining an Effective Technical Conscience," principle 4, "Engineers adhere to sound engineering principles," by not using applicable codes and standards in the design of the CCVT.

a. Plant design standards had not been updated for minimum creepage distance for HV insulators in contaminated environments to reflect industry codes and standards; and b. DCPP design engineers over-relied on PG&E and industry experts at the expense of industry codes and standards as it pertained to the selection of the creepage distance.

C. Contributing Cause

PG&E identified the following contributing causes:

(1) An inadequate mental model resulted in underestimating contamination levels due to the environment.

8 (2) The design of the Unit 2 Emergency Diesel Generators (EDG's) exhaust stacks contributes to the hydrocarbon contamination on the equipment in the Unit 2 MBT area.

(3) Weaknesses in planning and executing construction projects contributed to contamination on the equipment in the Unit 2 MB T area.

D. AFW Pump Setpoint The cause of the AFW pump setpoint procedure issue was a human knowledge based error.

IV. Assessment of Safety Consequences

There were no safety consequences as a result of this event. The transfer of plant loads to startup occurred as designed. Equipment necessary decay heat removal was available and operated as required by plant procedures.

The unexpected restart of the AFW pump did not challenge operator restoration actions or operational limits.

Unit 1 remained at full power and all vital buses remained powered by auxiliary power. Therefore, the event is not considered risk significant and did not adversely affect the health and safety of the public.

V. Corrective Actions

A. Interim Corrective Actions PG&E will take the following actions:

(1) Ramp the unit off line if arcing becomes visible on the CCVT with arcs increasing in diameter and spanning multiple sheds over the full length of the insulator, as these symptoms show that a flashover is highly likely.

YEAR

6. LER NUMBER I

SEQUENTIAL I NUMBER 2012

  • 002 REV NO.

00 6

3. PAGE OF 8

(2) Clean Unit 1 and Unit 2 CCVT's and LA's prior to the first rain in the fall of2013. Perform Effective Salt Deposit Density (ESDD) and hydrocarbon contaminant sampling, and as-found and as-left hydrophobicity tests while cleared.

B. Immediate Corrective Actions

The following immediate corrective actions relative to the CCVT's were taken following the CCVT failure:

(1) Replace the Unit 2 "A" Phase CCVT and perform Power Factor (PF) testing.

(2) Replace the Unit 2 "A" Phase LA and perform PF testing.

(3) Perform PF testing of the Unit 2 "B" and "C" Phase CCVT and LA.

(4) Clean the HV Polymer Bushings on the Unit 2 MBT "A" and "B" Phases ("C" Phase is ceramic) and clean the Insulators on the Unit 2 "A," "B," and "C" Phases CCVT's and LA's.

(5) Megger the secondary circuits of the Unit 2 "A" Phase CCVT (between the CCVT and CAL-ISO metering relays).

(6) Establish monthly corona-camera monitoring and weekly infrared monitoring to identify trends.

(7) Establish visible light camera to monitor Unit 1 CCVT's with real time video.

C. Corrective Actions to Prevent Recurrence PG&E will implement the following actions to prevent recurrence:

(1) Replace the CCVT's with an alternate design that meets IEEE C57.19.100 environmental creepage distance requirements and other electrical specifications, including appropriate insulator material.

(2) Revise plant design standards to reflect:

a. IEEE C57.19.100 and C57.19.01, "IEEE Standard Performance Characteristics and Dimensions for Outdoor Apparatus Bushings," guidance for creepage distance forall HV insulators including determination of contamination classifications; and b. IEEE 693 guidance for seismic criteria.

(3) Develop and present a lesson plan through Engineering Training to discuss the procedural requirements to review industry standards and codes when performing design work.

(4) Establish a two year contamination monitoring program to obtain baseline data. The program will consist of installing sample points (polymer insulator segments) in the Unit 1 and Unit 2 MBT areas. Samples will be taken periodically to measure the ESDD and hydrocarbon deposition rate, and total deposition. Samples are also to be taken on Unit 1 and Unit 2 MBT HV bushings, CCVT's, and LA's during refueling outages.

YEAR

6. LER NUMBER I

SEQUENTIALT NUMBER I 2012 -

002 REV NO.

00 7

3. PAGE OF 8

(5) Establish a requirement to implement construction dust mitigating measures when performing earth work, excavation, or any construction activities that may generate airborne contamination near the main bank transformer areas.

(6) Establish receipt-inspection criteria for HV polymer insulators to perform hydrophobicity testing per Swedish Transmission Research Institute (STRI) Guide 92/1, "Hydrophobicity Classification Guide."

(7) Replace the 230kV circuit switchers with an alternate design that meets IEEE C57.l9.l00 environmental creepage distance requirements including appropriate silicone insulator material and other electrical specifications.

(8) Update the maintenance program for the 230kV circuit switchers to revise the silicone grease replacement frequency to every two years.

(9) Revise design procedures to incorporate guidance on how to review industry codes and standards for content relevant to the design work being performed and use the standard's guidance as appropriate.

(10) Replace the 230kV start-up transformer bushings and LAs with an alternate design that meets IEEE C57.19.100 environmental creepage distance requirements including appropriate insulator material and other electrical specifications.

(11) Replace all porcelain MBT bushings with an alternate design that meets IEEE C57.l9.l00 environmental creepage distance requirements including appropriate insulator material and other electrical specifications.

D. AFW Pump Setpoint Corrective Actions (1) Update setpoint document to identify the relationship between the SG setpoint and the TD AFW pump actions.

(2) Tailboard Operations procedure writer staff on the event and the expectation to consult supporting documents when performing Emergency Operating Procedure modification scoping.

VI. Additional Information

A. Failed Components The DCPP Unit 2 MBT "A" phase CCVT bushing failed due to an insulator flashover.

B. Previous Similar Events

On August 16,2008, Diablo Canyon Unit 2 MBT "C" Phase experienced a catastrophic failure of the HV bushing.

A significant amount of porcelain shrapnel resulted from the failure. The debris damaged adjacent equipment and penetrated the northeast side of the administration building in multiple locations. Debris was also found in the parking lot several hundred feet away. The event occurred at 23:56 on a Saturday. The potential for injury was very high if the catastrophic failure of that HV bushing had occurred on a normal workday.

A root cause evaluation performed as a result of the MBT "C" Phase HV bushing failure found that catastrophic failure of bushings was not an uncommon occurrence. To improve personnel safety, a recommendation was made to replace the MBT porcelain bushings, the CCVT's, and the LA's with models made with a safer insulator material. Design changes were developed and components were replaced with models made of a silicone polymer insulator rather than porcelain. Bushings of Unit 2 MBT "A" and "B" phases were replaced with polymer in 2009.

The Unit 2 MBT "C" phase bushing remains of porcelain design. In Unit 2 Refueling Outage Sixteen, the CCVT's and LA's were replaced with polymer. In Unit 1 Refueling Outage Seventeen, the CCVT's and LA's were replaced with polymer. All three Unit 1 MBT's continue to have porcelain bushings.