ML20064K810

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Discusses Findings Gathered During 810617 Site Visit Re Facility Loss of RHR Capability During Apr & May 1981.Util Has Committed to Mod of Wash Screen Wash Sys by 1983. Attendance List,Chlorinator Outage Info & Drawings Encl
ML20064K810
Person / Time
Site: 05000000, Brunswick
Issue date: 07/22/1981
From: Imbro E
NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To:
NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
Shared Package
ML082180533 List: ... further results
References
FOIA-82-261 NUDOCS 8107300168
Download: ML20064K810 (19)


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ut UNITED STATES AE00/E119

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g NUCLEAR REGULATORY COMMISSIO,N a

"^ssinoTow. o. c. zosss This is an internal, pre-b decisional document not

- Jul:*1c2-1981 necessarily representing a position of AE00 or NRC.

M MEMORANDUM FOR:

File

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FROM:

Eugene Imbro and,Joan b annelli Office for Analysis and Evaluation of Operational Data

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SUBJECT:

LOSS OF RESIDUAL HEAT RE} OVAL ("liHR) CAPIBILITY AT BRUNSWICK t

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UNITS 1 AND 2 The purpose of this memo is to document our findings to date on the loss of

-4 RHR ac -Brunswick Units 1 and 2 that occurred during April and May 1981. %e majority of the information presented was obtained during the June 17, 1981 site visit with Carolina Power and Light Company (CP&L). Michael T. Masnik, NRR,' a fisheries biologist, accompanied us on the site visit and provided the necessary expertise on the biological aspects of the marine organisms.

Brunswick 1, which was shutdown on Apri) 17, 1981 to begin a scheduled maintenance outage, experienced a total loss of RHR on April 25 when the baffle

. plate w:ich divides the water box of RHR heat 4xchanger (HX) 1A failed thus allowing service water to bypass the HX tubes. RHRHX 1B was out of service for maintenance at the time as a result of a prior licensee commitment (LER-l 2-80-30). %e damsge was caused by excessive differential pressure across the baffle plate which resulted when a second RHR service water pump was started due to the degradation of, cooling capability observed by the operators. %e degradation of cooling capability stemmed from the buildup of shells and shell fragments from marine organisms which blocked the HX tubes. During the time l

that both trains of RHR were out of service an alternate cooling flow path I

was first established using the spent fuel pool HXs, the condensate storage tank, and the core spray system to provide makeup to the reactor vessel.

Later a flow path was established using the main condenser as a heat sink.

In this mode of cooling, the main steamlines were flooded and the water level in the condenser was raised above the tubes. Primary water was then circulated through the condenser using the turbine bypass valves. Before initiating this mode of cooling, however, the main steamline pipe hangers had to be pinned so that the weight of water in the flo'odad lines would not cause excessive I

deflection of the piping.

In order to return to a normal cooling flow path as expeditiously as possible, temporary repairs were performed. Rese consisted of cleaning the shells from the 1A RHRHX, jacking the baffle plate back into piisition and welding strong backs to the baffle plate for support.

As a result of the problems found on the Unit 1 RHRHXs a special inspection was performed on the Unit 2 RHRHXs. An ultrasonic exam? nation of RHRHX 2A indicated that the baffle plate was not displaced, however, flow tests indicated a higher than normal differentini pressure (DP) at design flow.

Similar examinations of RHRHX 2B indicated that the baffle plate was displaced. Both HXs were declared inoperable and Unit 2 was shutdown using RHRHX 2A at reduced capacity due to the fim.r hiockage.

After Unit 2 was in cold shutdown, the main n

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condenser was used as the heat sink as was done on Unit 1.

This allowed both RHRHXs to be taken out of service in order that they could be simultaneously repaired.

The RHRHXs at Brunswick are vertical "U" tube HXs and are arranged such that the water box is below the copper nickel (cu Ni) tubesheet.

The water box.

of the HX is carbon steel explosively clad with Cu-Ni and has a 70-30 Cu Ni baffle plate that separates the inlet and outlet service water flow. The one-inch thick baffle plate, fabricated from Cu Ni...is weldell on top to the tubesheet and on the sides to the water box. The bottom of the baffle plate extends approximate f 3/8 inch into a machined groove in the water box cover which along with the baffle plate to tubesheet veld provides lateral stiffness.

-The baffle plate is 54 1/2 inches wide and 44 3/4 inches high and can generate significant horizontal and bending forces even at relatively low DPs due to its large surface area. ~.' t was stated by the licensee that ASME Code allowable stress would be reached in the baffle plate at a DP of 10.4 psi. The licensee, however, was of the opinion that the deflections were caused by DPs between 50 and 100 psi since they had experienced DPs of 30 psi with no apparent damage to the baffle plate.

The inspection of the RHRHXs revealed the following:

Unit 1 RHRHX 1A The baffle plate,was displaced nine inches.

Unit 1 RHRHX IB I

The baffle plate was displaced nine_ inches and the side welds pulled loose to within eight to ten inches of the tubesheet.

i Unit 2 RHRHX 2A The baffle plate was intact.

-A layer of shells and shell fragments approximately 1/4 to 1/2 inch in depth was found on the inlet side of the water box cover.-

When held up against the tubesheet by the flow, these shells provided some flow blockage to approximately 60% of the tubes.

Unit 2 RHRHX 2B The baf fle plate was displaced approximately three inches at the bottom center.

The deflection started three inches from one side of the water box and extended to nine inches from the opposite side. The side welds were intact and a layer of shells and shell fragments from two to five inches deep was found on the inlet side of the water box cover. Approximately 50% of the tubes had some shell blockage.

Further examination of the service water system revealed that the 30-inch concrete lined nuclear and conventional service water headers were completely covered; principally, with marine organisms that are encidsed in a calcareous shell or test.

Species present included the American oyster, Blue mussel, barnacles, and serpulids (tubeworms).

The most frequently encountered u..

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non-calcareous organisms were hydrozoans and polycheate worms. The most common

. These organisms formed a layer species encountered was the American oyster.,f the pipe tapering off to 1/2 inch approximately one-inch thick on the bottom o on the top.

As was expected, more organisms were found in the larger diameter pipes, where flow rates are lower. (about 3.36 fps in the 30 inch header with s

one service water pump running) than in the smaller diameter pipes with higher flow rates.

Settlement of marine fouling larvae is dependent on flow velocity and larvae have difficulty attaching if the flow velocity is above four fps.

It,was also noted that the accumulation of organisms decreased proportionately with the distance from the intake structure.

This may be due to the existence of an unfavorable temperature gradient or a depletion of the food _ supply._ Pides which are normally is' lated were, for the most part, fodnd to be clean.

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Isolated portions of the system including the RHRHXs are generally layed-up with well water.

Detailed information on the location and extent of marine growth is shown in Figure 2.

Live organisms were not found in the RHRHXs, only shells and shell fragments.

The reason for this is the Cu Ni water box surfaces.are toxic to marine organisms and the Cu Ni prevents attachment and growth. Although it was indicated that.in some cases 50 to 60% of the RHRHX tubes had some flow blo'ckage, the actual amount of debris removed from the tubes amounted to approximately one cup per HX as compared tb the several gallons of shells found in some of the inlet water boxes. The shells are preferentially swept into the RHRHXs since they are at a low elevation (ten foot) in the reactor building and form a trap in the service water system. The service water is supplied to the RHRHXs from.

the 50-foot elevation whe're the RHR service water pumps are located. After leaving the RHRHX, the service water piping returns to the 50-foot elevation before exiting to the circulating water discharge canal.

Shell growth was not detected in the four diesel generator heat exchangers or.in the core spray pump room cooler; however, approximately one handful of shell fragments was found in each of these heat exchangers.

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Some shells were found in the turbine building component cooling water (TBCCW) heat exchangers, however, these are not safety-related components. Like the reactor building component cooling water (RBCCW) heat exchangers, the TBCCW heat exchangers can be periodically taken out of service, inspected, and cleaned as needed.

With the exception of the polycheate worms, all organisms listed above securely attach themselves to the inside surface of the pipe.

Even after death the calcareous tests (shells) of the oysters, barnacles, and serpulids (tubeworms) remain attached providing an ideal substrate for subsequent larval settlement

. and the growth of new organisms. The only way the attached tests from either live or dead organisms can be removed from the piping is by mechanical means, flushing is totally ineffective.

Some organisms, such as the Blue mussel will eventually release from the substrate after death.

American oysters will lose their top shell after death.

The shells which are released from the substrate will be swept through the piping.

As a first step in cleaning out the piping, the licensee flushed the Unit 2 nuclear service. water header for '40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> *with heavily chlorinated water prior to cleaning.

The Unit 2 conventional header was chlorinated for 190 hours0.0022 days <br />0.0528 hours <br />3.141534e-4 weeks <br />7.2295e-5 months <br /> and

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flushed for 260 hours0.00301 days <br />0.0722 hours <br />4.298942e-4 weeks <br />9.893e-5 months <br /> using the RBCCW HX water boxes as a collection point then, hells.

for s Figure 1 shows the chlorination and flush paths for the conventional i

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and nuclear service water headere. Since sheIV were still found aft'er 2,60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />, the licensee concluded that cleaning the system by flushing was ineffective and resorted to mechanical cleaning.

Workers entered the Unit 2 nuclear header in the service water building and mechanically. scraped the pipe walls.

As previously mentioned, an inch of shells was found at the bottom of the pipe.

This tapered off tp one-half inch of.

shells at the top. The header was then back fibshed and' the shells were washed -

out onto th'e service wate'r" building floor.

The conventional header and the i

smalier pipes were Hydrolazed (a process utilizing water sprayed through a nozzle at 8,000 to 10,000 psi).

Figures 2, 3, 4, and Table 1 give more details as to

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where and what types of shells were found and how each section of pipe was cleaned.

During the initial startup of Brunswick, shells and shell fragments were found in the service water and circulating water systems. At that time, there were no provisions-for chlorinating.. A study was begun which con'cluded that chlorination would provide an effective means of controlling marine growth in the plant. A 3

chlorination program was begrn in the Spring / Summer of 1975 (prior to commercial operation of Unit 2) which. called for continuous chlorination of the service j

water, except during times when the screen wash pumps were operating, and i

chlorination of the circulating water for two hours a day.

This amounted to i

adding 300 pounds of chlorine a day for each service water pump that was operating, yielding a free residual chlorine concentration of about 1 ppa at the. ~

RH4 heat exchangers and an undetectable concentration at the plant; discharge due

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to the dilution with the circ'ulating water from the main condensers.- Figures 5 and 6 show the chlorination system.

As can be seen from Table. 2, the chlorination-e was stopped during the Spring /Sutuisr 1980 outage.- This was done primarily to protect employees from being overcome by chlorine while working near the intake i

or on the associated piping.. During the 1980 Summer outage, a fine mesh screen (1 mm) was temporarily added to one. bay of the circulating water intake on a trial basis in an attempt to reduce fish entrainment. In going from the 3/8 inch mesh to the one millimeter mesh, continuous screen washing was required.

Chlorination was reinitiated in November 1980, after overcoming a series of mechanical and ele.ctrical problems.

This resulted in a high fish kill due to the proximity of the chlorination piping and the screen wash pump suction in the intake bay. The highly chlorinated water being taken up by the screen wash 4

system is discharged into the intr.ke canal after performing its screen wash function. To eliminate this problem a dike was installed, in April 1981, in the i

1-A service water bay between the service water pumps and the chlorination piping (see Figure 6).

Chlorination was reinitiated cn May 10, 1981 by this time the chlorination had been stopped for approximately 14 months. This 1

corresponds with the size of the oyster shells that were found.

The largest i

oysters were approximately 1 to 1 /12 inches in total length or about one year old.

4 Since the amount of loose shells and shell fragments found in the heat exchangers was relatively small compared to the amount of oyster growth in the service water headers, it is thought that, statistically, some small percentage of the 3

organisms, principhily young oysters, (they can live as long as 40 years) died for whatever reason, and as their shells detached they were swept, by the flow in 4

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the piping,'into the heat exchangers where they.oradually accumulated.

Eventually, the shells and shell fragments impinged on the tubesheet and were held blocking

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the tubes by the differential pressure between*the inlet'and outlet water box.

As the number of tubes blocked increased, the differential pressure became greater until ultimately, the baffle plate became displaced.

Following the cleaning operations, the buckled RHR heat ' exchanger baffle plates were replaced and the heat exchangers were returned to their original design specifications (see Figure 8).

Due to,,the Cu N,1 used 14 these components, neither the welds nor the baffle plates

  • thenselves are as strong as in HXs in other plants with carbon steel baffles and water boxes.

Figure 7 illustrates the deformation found in the heat exchangers and Table 3 summarizes the work which has been performed.

In addition, a monitoring program has been initiated at Brunswick (see Table 4).

The RHR heat exchangers will be tested monthly, at which time the flow rate and DP across the heat exchangers will be measured.

The licensee stated that a sharp rise in DP would be expected as shells accumulate in the heat exchanger.

The RBCCW and TBCCW heat exchangers will continue to be periodically inspected.

The service water' headers will also be inspected on an annual basis.

CP&L has made a commitment to modify the screen wash system by 1983J Fine mesh

screens (1 mm) will be permanently installed in the circulating water bays and unchlorinated water will b,e us,ed for the screen wash... '1he service water system will retain the 3/8 inch mesh screens. All of these screens are Cu Ni.

--- [Wmff Eugene Imbro Office for Analysis and Evaluation of Operational Data ~

Joan Giannelli Office for Analysis and Evaluation of Operational Data

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C. Michelson J. Heltemes J. Crooks R. Baer, IE W. Mills, IE J. Olshinski, NRR G. Holahan, NRR J. VanVliet, NRR D. Johnson, I.E M. Pasnik, NRR

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l. inn N3 Frc:3 To Gr:w' i Grt.wth Cleined Comm::nto SW-103-30-157 Inteke 90 Elb:w 50' us vy 1"

,Battom of pips Yes Crewth w a moat,.i 0

El Rx Bldg Botto Tapp: ring Oyetero 74%

Scraping abundrnt neer intake tapered to 1/,2" on top Mytilus 17%

off proportionally, Darnacles 1%

8.ide of pipe with the distance Oysters 91.4%

from the intake

,Hylitus 1.1%

>W-29-18-157 Nuclear Hender Just past Moderate-light At inlet Tes Crowth was most (10') V255 1/2" all the way Oysters 90.6%

Uydrolaze abundant near around ID of the Polychcates 8.2%

inl,et tappered off to 1/ft2 at pipe valve V255 toward Diesels (1/2 shell/ft2) 5W-1-20-157 2A CSW Discharge 2-SW-V14 Light-mnderate On valve V14 Yes 5W-2-20-157 2B CSW Discharge 2-SW-V16 6-8 oysters per 11 oysters hydrolaze NoIgrpwth wan found between the SW-3-20-157 2C CSW Discharge ifoot squared 3 tube worms barnacles ptunp dincharge

& t'he check l

hydrozoan valves. All growth was found between the check valves &

the nuclear &

conventional i

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headers' SS-4-20-157 2ANSW Discharge 2-SW-V19 light to none small oysters No Arcas around-

- barnacles,. tub e.

e ere SW-5-20-157 2BNSW Discharge 2-SW-V20 other areas did not need cicaning bet ArcEearUca0er6 Yes SW-117-6-157 Nuclear header Valve Heavy to light SameSW 03-Scraping nuc 2-SW-Y117 30-157 valve V116 was scrapped, the area between V117 & VHf-did not need cienning TABLE I

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.Crowth Crewth Cic ntd Coum:nto 0

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N-103-30-157 90 Elb w 501 2-SW-V105 &

Hodcrate SidNf pipa Yda 1 icycr of El Rx b1dg V103 Oystere 64%

Screping grcwth en bottom of pipe Mylitus 35%

i bottom of pipe 50% coverage of Mylitus 6%

sides Barnacles 12%

& top some oyster bottom shell halfs on sides sW-103-24-157 2-SW-V105 2-SW-V102 light.to Oysters &

No' Very few oysters none barnacles or'other growth found. This is i

generally a stag-nant line sW-106-20-157 22-SS-V106 2-SW-V193 light to Oysters &

No Piheelevation.'

none barnacles for this section obtained from a cogiparison to Unit #1' e

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sW-107-14-157 2B RBCCW lix 2-SW-V108 light to hydrozoan &

No Scattered barn-none barnacles acle growth paty ches 3 to 4 in.

No oysters found t

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sW-234-6-157 2-SW-V275 DG#4 IIx None None No 4

No attached marine growth.

All shells were older & appeared to have been

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washed in.

sW-100-30-157 Intake 2-SW-V3 IIeavy 1" Same as Yes crowth tapered Bottom tapering Nuclear licader Hydrolare off no ortional to 1/2" top

& Scraping to t e istance from the intake lH-100-24-l'i7 Conventional 25 to 308 Moderate

Oysters,

'Yes Cgow g as most llender (rom header barnacica,

[1y g aze jnSet&tpcEcb tubeworms

& some mylitus scraping off rapidly Tfl8LE I

(C6HTINogn)

TABLE 2.

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Chronology of Chlorinator Outage 4'

-February 22,1980 - Train #4 shutdown due to mechanical and electrical problems.

-March 15,198.0, to September 21,~1980 - Unit Nos. '.1 and 2 outages. [wat)

-September 1980 - Restart of Chlorinator System failed due to electrical

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problems with heaters and controls.

-October 1980 - Restart of Chlorinator' System revealed holes in the' evaporators.

Evaporators were replaced.'

-October 31, 1980 - The Chlorinator System was run for three days.

The system was shut down because of fish kill.

-November,1980 - Attempts were made to operate the system in a manner that would not kill fish.

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-December 1980 - Contacts were.made with involved groups to resolve the problem of chlorine in the screen wash.

-January 1981 - Trouble ticket submitted to have dam installed.

-March 1981 - A secorid trouble ticket was submitted.

-April 1981 - The dam was installed in 1A' service, water bay.

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-May 1981 - System,ine up was completed.

Held up start up due to oysters in heat exchangers.

-May 10,1981 - Rutarted chlorination.

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The following is a brczkdsvn of the work performed on both Unit 1 ank

' Unit 2 RHR heat exchangers:

2A RHR Heat Exchanger

  • Spring 1980

- Heat exchanger inspected and' inlet and outlet elbows replaced (PM 79-232T).- Baffle plate inspected and,gdegradation noted.

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13 May 81

- Heat exchanger drained.

Baffle plate inspected with no signs of deformation.

Exchanger cleanad of shells and put back into service 14 May'81.

3 Jun 81

- High AP noted across baffle plate.

Exchanger cleaned of shells, no signs of deformationeturned to service 4 Jun 81. i 2B RHR Heat Exchanger l Spring 1980 - Heat exchanger inspected and a 9 inch deflection discovered ~ in baffle plate. Vertical plate attachment welds cracked N 33 inches. Baffle plate and elbows replaced per PM 79-232s and returned to service. y 6 May 81 - Exchanger drained and inspected. A 3 inch. deflection of plate noted. Fillet welds along side walls showed one 2 inch crack. I Baffle plate removed and heat exchanger bolted up and put back into service on 9 May 81.. Unit used_ as flow path without plate.with heavy chlorination of service water system. 16 May 81 - Exchanger drained and lower channel he'ad once ag'ain removed so that baffle plate replacement work could begin. Work completed on 24 May 81 and returned to service. i 1A RHR Heat Exchanger 25 Apr 81 - Lack of heat transfer noted by Operations. Heat exchanger [ ' drained to flow and channel head removed. A 6,to 9 inch deflection noted and plate jacked into position with porta-powers. Bracing stays welded to back of plate for temporary support. Heat exchanger head reinstalled and put back into service 27 Apr 81. I I 2 Jun 81 - Exchanger drained and lower channel head removed. Permanent repair replaced baffle plate and inlet and outlet elbows per PM 79-231T. Work completed on 13 Jun 81. Awaiting reinstallation of inlet isolation valve (removed for vessel - hydro) before returning to service. l IB RHR Heat Exchanger k i 12 Apr 81 - Heat exchanger drained and inspected. A deflection of 8 to 9 inches noted on baffle plate. Plate replaced along with inlet l l and outlet elbows via FM 79-231G. Work compelted on 31 May 81 and returned.to service. l 3 Jun 81 -HighAPnotedacrossbaffle[ late. Plans are to drain and i remove channel head in order to clean shells - tentatively

Heat Exchanger Monitoring Program I. Short Term RHR Heat Exchangers +- Divider plate AP monitoring ~ Verification of design AP Trend analysis of AP Heat transfer evalu'ation ~, Other Safety Related Heat Exchan'gers Internal inspections II. Long. Term RHR Heat Exchangers Periodic test for ~ checking AP Other Safety Related Heat Exchangers Periodic tests requiring internal inspection

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