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April 9, 2014 Pressurizer Heaters get reworked after...

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Stairs and Handrails Always use handrails where provided on stairs or stairways. Take‐A‐Minute to iden- tify deficiencies with stairs and handrails and report them to your Supervision or write a Condition Report as required. Confidential and proprietary. For internal distribution and use only. 1RE18 Goals Goal Actual Safety CAQ-S or higher shutdown safety events in Key Safety Functions 0 0 Unplanned color changes in Key Safety Functions 0 0 Level 1 or 2 ECO or Plant Status Control events 0 0 Lost time or restricted duty injuries 0 0 CAQ-S safety events in Dropped Items, Crane Manipulation or Electrical Safety 0 0 ALARA Outage Dose 34 rem 24.234 Personal Contaminations 35 12 CAQ-S High Radiation Area access control events 0 0 Financial Excellence Outage Duration (days) 61 days 25 Budget Performance (weekly status) $49.3M 49.1M Equipment Reliability CAQ-S Foreign Material Exclusion events 0 0 Completed outage work scope >=98% / Plant reliability index for 30 days after breaker closed >=85 / April 9, 2014 Day 24 Pressurizer Heaters get reworked after inspections As of Wednesday afternoon, Unit 2 was at 100% power. We continue to operate the unit safely. As we started an Open Loop Auxiliary Cooling Water pump earlier, we showed indications that our discharge valve was closed – it was required to be open. This will be a station clock reset, and a Plant Status Control event. We are investigating the condition. Unit 2 is in Mode 5 with coolant tempera- ture stable at approximately 98 degrees. Vessel level is 37’4” with B and C Residual Heat Removal trains are in service, and they are the protected trains. A-train work window is currently open. In other on-going activities, our Main Generator core measurement continues, and we are scheduled to perform a 2-hour thermal-vision test looking for hot spots. Chemical and Volume Control System (CVCS) Charging Flow Control Valve FCV- 0205 work will be completed the end of this week with no issues anticipated. The refuel- ing team has removed the control console, and Core Exit Thermocouple connections are complete. We are scheduled to perform an adjustment on the auxiliary hoist on the refueling machine. Containment off-load continues. Final containment building Equipment Hatch closure is scheduled for Friday morning, with the leak rate test commencing shortly afterwards. We are doing a great job controlling costs – we are spending the money when and where we need to. Thanks to all for staying focused in this area. WE SFTY Phase 1 wrapping up, generator work continues During a 1RE18 Electrical Maintenance inspection of the pressurizer heaters, a significant number of the heater termination sleeves were found to be in a degraded condition. Also, several heaters exhibited chips on the ceramic insulators located at the terminations, and a broken lug was discovered on two separate heaters. These sleeves and ceramic insulators are required to maintain electrical isolation between the heater terminals, and are important to monitor. Of the 117 sleeves, 44 exhibited signs of physical degradation, and several ceramic insulators exhibited chips. A review of photographs revealed a large gap in thermal insulation exposing the protective sleeving to heat from the pressurizer metal surfaces above 600 degrees. The exposure varies directly with how close the sleeving is to the insulation gaps – this is the apparent cause of this condition. However, the sleeving degradation and ceramic chipping are currently having no adverse effects. There is operational impact on the pressurizer heaters with the broken lugs, and although there is no impact from the condition of the sleeves and chipped ceramic insulators, the current status of these sleeves and insulators raises the question that a condition could develop that would compromise the desired level of electrical isolation between the heater terminals prior to the next Unit 1 outage. If this occurred, additional heaters could become inoperable and reduce the capability of the pressurizer to perform its designed function. The pressurizer is a tank that is connected to and is part of the Reactor Coolant System. This pressurizer is normally about half full of water during power operations. It houses electric submersible heaters, located at the bottom, which are designed to heat the water inside, to the point where a steam bubble forms at the top. The more heat that is added, the higher the pressure produced inside. At our normal operating pressure of 2250 psig, we are able to heat the reactor coolant to approximately 600 degrees without boiling. The pressurizer is essentially a tank with sub- mersible heaters, designed to form a steam bubble at the top to pressurize the reactor coolant system. Continued on page 2
Transcript
Page 1: April 9, 2014 Pressurizer Heaters get reworked after ...storage.cloversites.com/stpnuclearoperatingcompany1/documents/STP... · (CVCS) Charging Flow Control Valve FCV- ... designed

Stairs andHandrails

Always use handrails where provided on stairs or stairways. Take‐A‐Minute to iden-tify deficiencies with stairs and handrails and report them to your Supervision or write a Condition Report as required.

Confidential and proprietary. For internal distribution and use only.

1RE18 GoalsGoal Actual

Safety

CAQ-S or higher shutdown safety events in Key Safety Functions

0 0

Unplanned color changes in Key Safety Functions

0 0

Level 1 or 2 ECO or Plant Status Control events

0 0

Lost time or restricted duty injuries

0 0

CAQ-S safety events in Dropped Items, Crane Manipulation or Electrical Safety

0 0

ALARA

Outage Dose 34 rem 24.234

Personal Contaminations

35 12

CAQ-S High Radiation Area access control events

0 0

Financial Excellence

Outage Duration (days)

61 days 25

Budget Performance (weekly status) $49.3M 49.1M

Equipment Reliability

CAQ-S Foreign Material Exclusion events

0 0

Completed outage work scope

>=98% /

Plant reliability index for 30 days after breaker closed

>=85 /

April 9, 2014

Day 24

Pressurizer Heaters get reworked after inspections

As of Wednesday afternoon, Unit 2 was at 100% power. We continue to operate the unit safely.As we started an Open Loop Auxiliary

Cooling Water pump earlier, we showed indications that our discharge valve was closed – it was required to be open. This will be a station clock reset, and a Plant Status Control event. We are investigating the condition.Unit 2 is in Mode 5 with coolant tempera-

ture stable at approximately 98 degrees. Vessel level is 37’4” with B and C Residual Heat Removal trains are in service, and they are the protected trains. A-train work window is currently open.In other on-going activities, our Main

Generator core measurement continues, and we are scheduled to perform a 2-hour thermal-vision test looking for hot spots. Chemical and Volume Control System (CVCS) Charging Flow Control Valve FCV-

0205 work will be completed the end of this week with no issues anticipated. The refuel-ing team has removed the control console, and Core Exit Thermocouple connections are complete. We are scheduled to perform an adjustment on the auxiliary hoist on the refueling machine.Containment off-load continues. Final

containment building Equipment Hatch closure is scheduled for Friday morning, with the leak rate test commencing shortly afterwards.We are doing a great job controlling costs

– we are spending the money when and where we need to. Thanks to all for staying focused in this area.

WE SFTY

Phase 1 wrapping up,generator work continues

During a 1RE18 Electrical Maintenance inspection of the pressurizer heaters, a significant number of the heater termination sleeves were found to be in a degraded condition. Also, several heaters exhibited chips on the ceramic insulators located at the terminations, and a broken lug was discovered on two separate heaters. These sleeves and ceramic insulators are required to maintain electrical isolation between the heater terminals, and are important to monitor. Of the 117 sleeves, 44 exhibited signs of physical degradation, and several ceramic insulators exhibited chips. A review of photographs revealed a large gap in thermal insulation exposing the protective sleeving to heat from the pressurizer metal surfaces above 600 degrees. The exposure varies directly with how close the sleeving is to the insulation gaps – this is the apparent cause of this condition. However, the sleeving degradation and ceramic chipping are currently having no adverse effects.

There is operational impact on the pressurizer heaters with the broken lugs,

and although there is no impact from the condition of the sleeves and chipped ceramic insulators, the current status of these sleeves and insulators raises the

question that a condition could develop that would compromise the desired level of electrical isolation between the heater terminals prior to the next Unit 1 outage. If this occurred, additional heaters could become inoperable and reduce the capability of the pressurizer to perform its designed function.

The pressurizer is a tank that is connected to and is part of the Reactor Coolant System. This pressurizer is normally about half full of water during power operations.

It houses electric submersible heaters, located at the bottom, which are designed to heat the water inside, to

the point where a steam bubble forms at the top. The more heat that is added, the higher the pressure produced inside. At our normal operating pressure of 2250 psig, we are able to heat the reactor coolant to approximately 600 degrees without boiling.

The pressurizer is essentially a tank with sub-mersible heaters, designed to form a steam bubble at the top to pressurize the reactor coolant system.

Continued on page 2

Page 2: April 9, 2014 Pressurizer Heaters get reworked after ...storage.cloversites.com/stpnuclearoperatingcompany1/documents/STP... · (CVCS) Charging Flow Control Valve FCV- ... designed

Outage Milestones:Phase 1 Complete - 1600, April 10Enter Solid Plant Ops - 1100, April 14

Transition to Phase 2 Meeting ScheduleBeginning Friday, April 11, the station will transition to a Phase 2 meeting schedule. Major changes include: the 0630 Operational Focus Meeting in the Unit 1 OSS conference room will now focus on both units; beginning Monday, April 14, we will return to the 0900 Daily Operational Focus Meeting (Monday – Thursday); there will no Noon outage meeting (Monday – Thursday). On the weekends, the 0800 weekend call (Friday – Sunday) will be replaced with an 1100 Unit 1 status meeting (Location MOF N201). For a complete Phase 2 meeting schedule, please consult today’s DOF package.

Gator Grill to Resume Normal HoursThe Gator Grill will resume normal hours (0630-0800 and 1100-1300) beginging tomorrow, April 10.

Developing and aligning goals for 2014Deadline for entering performance goals into SuccessFactors is May 1. As you work with your manager/supervisor, keep in mind to align goals with the overall company goals and ensure they reflect current roles and responsibilities. Set SMART goals. For more information, send email to [email protected].

MyData Expense Types ChangeTo simplify employee expense processing you will notice changes to the “travel” Expense Types in MyData Expenses. The travel Expense types have been changed to Rental Car, Lodging, and Airfare – Emp Business Travel. It is no longer necessary to code to an Expense Type for OFB Booked vs Non-OFB Booked. However, when using the Company STP Orbitz for Business (OFB) site for travel arrangements, you must send the STP OFB reservation confirmation with the barcoded coverpage to RMS. If you book outside of OFB (or Out of Policy through OFB), you must send the completed STP Form 8080 with the barcoded coverpage to RMS. STP and Volunteer ScholarshipsHR is accepting applications for both the STPNOC Scholarship and the Volunteer Scholarship. If you are an STP employee with a dependent going to or currently attending college, fill out STP Form 7763 and STP Form 7764 located on the R drive under FORM_STP. Send completed forms to Clarence Fenner. The deadline for submittal is April 15.

STP Notes

O-61N-31

Get your Bingo card with a $5 donation: Credit Union - NSC, ext. 8995; Nuclear Notions - NSC, ext. 4007; First Service Credit Union, ext. 8995; Ellen Farmer, ext. 4680; Velma Smith, ext. 4343; Joyce Brunnemann, ext. 8237;

Mary Dykes, ext. 4211; or Barbara Carnley, ext. 7571

Play 1RE18 Bingo for United Way!

Submit winning cards via interoffice mail to Outage Times, NSC Mail room with your name and mail code to be eligible for a prize drawing.

All proceeds donated to Matagorda County

United Way.

This allows large amounts of steam to be produced for our main turbine.

After a thorough evaluation, we scheduled replacement of the cracked sleeves. Ceramic chipping was also reviewed, and it was determined that the heaters are acceptable for use as long as resistance testing is satisfactory. Further examination of photos and discussion with Westinghouse produced similar conclusions. This testing met acceptance values.

We have reworked the broken lugs and insulators, completed degraded sleeve replacements, re-terminated the cabling, re-insulated the heaters, and will perform a final closeout inspection, anticipating safe and event-free operating cycles. In addition, this thermal insulation gap condition also applies to the Unit 2 pressurizer heater connections and warrants inspection in 2RE17.

Pressurizer Heaters......................Continued from page 1

1RE18 outage dose goal revision approvedThe ALARA Review Committee (ARC) met

Monday, April 7, to review 1RE18 dose performance. The committee approved a dose reduction of 9.0 Rem to the outage dose goal, making the revised dose goal 34 Rem. Several factors went into changing the dose goal including reduced outage scope, a reduction of dose rates on the 68’ due to non-rapid refueling, lower source term and a reduction in man hours to get outage jobs completed.

“The revised goal is very achievable. A lot

of time and effort was spent determining the new goal,” said ALARA Supervisor Terry Farrand.

The outage dose goal is one of our primary outage goals and is set at the beginning of the outage. The radiation levels in the plant, what we call source term, are used to develop the dose projections and develop the outage Dose Goal. The source term has been steadily dropping, each outage, as a result of zinc injection, which began in Unit 1 in June 2009.

STP participates in an INPO Evaluation and Assessment every two years. Every four years the World Association of Nuclear Operators (WANO) leads the evaluation. This year, WANO will lead STP’s evaluation, scheduled July 21 – Aug. 1. The areas of focus, methods and criteria are identical to INPO Evaluations.

A series of visits will precede the evaluation and assessment. On Thursday, April 10, INPO’s Greg Bradley will be onsite to conduct an Operations assessment. A Maintenance and Work Control team visit took place during the week of March 23.

On Monday, April 14, a Radiation Protection team evaluation begins. The week of June 16, a tentative Team Lead visit is scheduled. Crew Performance Evaluations will be held

June 23-27. The final exit meeting is planned for Sept. 9.

“An evaluation of our performance is already underway with these visits,” said Plant General Manager Louis Peter. “We have a strong team and we’ve worked hard on improving since our last evaluation.”

Every evaluation team has responsibilities to identify station strengths to share with the industry. The key

focus areas are Operations, Maintenance, Work Scheduling, Equipment Reliability, Chemistry, Configuration Management, Radiological Protection, Industrial Safety, Performance Improvement, and Organizational Effectiveness.

STP also will have its first INPO Corporate Evaluation in November.

WANO Operations Evaluation visit Thursday

Greg Bradley

Because of the momentum the Oz Ac-countability Principle training has gained across the station, STP has negotiated with Partners in Leadership to provide an accelerated training campaign for STPNOC employees.

Following the conclusion of 1RE18, all STNOC employees will go through the Oz training between May 27 and June 26.

Please sign up for one of the sessions using LMS prior to May 15.

Personal and organizational accountabil-ity is a key focus area for the station. It is an expectation that all employees attend one of these training sessions.

The course is Oz Principle Accountability Training, code HRD077. The training ses-sions will be conducted beginning Tuesday,

May 27, from 0730 to 1600 at the Center for Energy Development Joint Information Center Media Room.

If you have questions or need additional information, please contact Laura Brieden at ext. 8097.

Click here for a complete schedule of classes.

Sign-up open for OZ Accountability Principle training sessions


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