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Nuclear Plant Journal - Digital Versions

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of balance-of-plant corrosion products.<br />

This ceiling results from the logistical<br />

limitations of maintaining hundreds of<br />

cubic feet of ion exchange resins with a<br />

fi xed total exchange capacity, deployed in<br />

numerous polisher vessels, in the requisite<br />

H-OH chemical form.<br />

Millstone Chemistry determined that<br />

the problem could only be addressed by<br />

resolving the competing goals of high<br />

secondary pH and H-OH form condensate<br />

polisher operations. Millstone conducted<br />

bench top testing to determine if operating<br />

the condensate polishers in the amine<br />

(ETA) form might be a viable option. A<br />

mixed bed test column was set up for the<br />

purpose of evaluating the performance<br />

of DOW 650C cation resin that had been<br />

converted to the amine form, along with<br />

550A anion resin in the conventional OHform,<br />

during a simulated seawater leak.<br />

Implementation of this experiment<br />

required questioning the standard industry<br />

practice that selectivity is the dominant<br />

ion exchange mechanism between the<br />

liquid phase (condensate) and the solid<br />

phase (resin). Successful completion of<br />

this test would require displacement to<br />

Confi dent to...<br />

Continued from page 27<br />

• Implementing low Cobalt 316 LN<br />

for the Primary Loop Piping, thus<br />

mitigating potential (IGSCC and<br />

TGSCC) issues as well as reducing<br />

Man Rem exposures during maintenance<br />

outages<br />

• Implementing single piece forging<br />

technology for the hot leg with side<br />

nozzles to eliminate welds and inservice<br />

inspections<br />

• Implementing chrome- moly- and<br />

copper-containing steel grades in<br />

the Main Steam Piping, mitigating<br />

potential Flow Assisted Corrosion in<br />

the steam piping<br />

The AP1000 component design,<br />

material selection, fabrication processes<br />

factor in lessons learned from operating<br />

experience, best practices and knowledge<br />

from industry materials research programs.<br />

Because of these factors, Westinghouse<br />

has confi dence that the AP1000<br />

will deliver reliable performance of com-<br />

be considered the dominant exchange<br />

mechanism, not selectivity.<br />

The bench top test was successful in<br />

proving that amine form resin would provide<br />

the same level of protection to the<br />

steam generators from seawater ingress<br />

as the conventional H+ OH form resins.<br />

This successful testing shattered all<br />

previous beliefs and paved the way for<br />

this innovation in condensate polishing<br />

operations.<br />

Productivity/Effi ciency:<br />

The advantages of amine operations<br />

go well beyond cost savings, safety improvements<br />

and less environmental impact,<br />

as it also allows for greater operational<br />

fl exibility.<br />

While traditional H-OH charges required<br />

a cation regeneration approximately<br />

every forty million gallons and an anion<br />

regeneration approximately every fi ve<br />

hundred million gallons, amine charges<br />

merely require a mechanical cleaning every<br />

two to three billion gallons. Imagine<br />

the operational fl exibility associated with<br />

decreasing the need to perform work on<br />

a resin charge from approximately ev-<br />

ponents in the next generation of nuclear<br />

power plants.<br />

9. What are recommended practices<br />

for reactor pressure vessel in-service<br />

inspection to ensure that:<br />

a. Entire thickness of the reactor<br />

pressure vessel is inspected from different<br />

angles.<br />

The regulatory requirements for reactor<br />

pressure vessel in-service inspection<br />

mandate that only the welds and a defi ned<br />

amount of adjacent base metal be examined.<br />

Such examinations are volumetric<br />

(ultrasonic testing) and include the entire<br />

thickness. The examinations are conducted<br />

from the inner diameter surface<br />

of the reactor vessel and are designed to<br />

examine the full thickness in thickness<br />

zones. Different angles and techniques<br />

are defi ned for each zone.<br />

b. Nozzles and their associated<br />

welds are checked<br />

Nozzle-to-shell welds, nozzle innerradius<br />

regions and nozzle-to-pipe welds<br />

are examined in accordance with regulatory<br />

requirements.<br />

ery ten days to approximately every two<br />

years. Using all H-OH demineralizers<br />

Millstone was regenerating each charge<br />

on a ten day rotation; this meant one regeneration<br />

needed to be performed every<br />

thirty six hours. With the advent of amine<br />

operations we now have the luxury of not<br />

working certain resin charges for almost a<br />

two year period. This allows for the fl exibility<br />

to perform almost all corrective<br />

and preventative maintenance on-line,<br />

thereby reducing the impact and need for<br />

valuable resources to be used during outage<br />

periods.<br />

In addition, this reduction in regenerations<br />

reduces the operator time spent in<br />

the condensate polishing facility (CPF).<br />

Millstone has seen an almost 40% reduction<br />

in operator time required to support<br />

daily CPF operations.<br />

Contact: Lewis Crone, Millstone<br />

Power Station, Chemistry Department<br />

465/5, Rope Ferry Road, Waterford,<br />

CT 03685; telephone: (860) 444-5722,<br />

email: Lewis.E.Crone@dom.com. �<br />

c. Detecting fl aws in the welds in the<br />

reactor pressure vessel.<br />

Due to the safety importance of reactor<br />

pressure vessel welds, requirements<br />

dictate that the examination methods provide<br />

a high degree of reliability. To ensure<br />

this reliability, the examination procedures<br />

are required to undergo blind performance<br />

demonstration tests proctored<br />

by a third-party organization. Such tests<br />

involve representative component mockups<br />

containing implanted defects that are<br />

representative of postulated defects. The<br />

procedures must be demonstrated to detect<br />

100 percent of the critical defects. Once<br />

the procedure is demonstrated, then ultrasonic<br />

test personnel who are responsible<br />

for the examination must also undergo<br />

blind testing using the same set of mockups.<br />

Blind testing means that the defect<br />

population within the mock-ups remains<br />

unknown to the participants. This performance<br />

demonstration protocol ensures a<br />

higher integrity of examinations.<br />

Contact: Scott Shaw, Westinghouse<br />

<strong>Nuclear</strong>, 4350 Northern Pike, Monroeville,<br />

PA 15146, telephone: (412) 374-6737,<br />

email: shawsa@westinghouse.com. �<br />

<strong>Nuclear</strong> <strong>Plant</strong> <strong>Journal</strong>, March-April 2009 www.nuclearplantjournal.com 41

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