Information Notice 1994-79, Microbiologically Influenced Corrosion of Emergency Diesel Generator Service Water Piping: Difference between revisions
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UNITED STATES | ===UNITED STATES=== | ||
NUCLEAR REGULATORY COMMISSION | NUCLEAR REGULATORY COMMISSION | ||
OFFICE OF NUCLEAR REACTOR REGULATION | ===OFFICE OF NUCLEAR REACTOR REGULATION=== | ||
WASHINGTON, D.C. 20555 | |||
===November 23, 1994=== | |||
NRC INFORMATION NOTICE 94-79: | |||
===MICROBIOLOGICALLY INFLUENCED CORROSION OF=== | |||
EMERGENCY DIESEL GENERATOR SERVICE WATER PIPING | EMERGENCY DIESEL GENERATOR SERVICE WATER PIPING | ||
==Addressees== | ==Addressees== | ||
All holders of operating licenses or construction permits for nuclear power | |||
All holders of operating licenses or construction permits for nuclear | |||
reactors. | reactors. | ||
| Line 39: | Line 39: | ||
notice to alert addressees to degradation resulting from microbiologically | notice to alert addressees to degradation resulting from microbiologically | ||
influenced corrosion in carbon steel piping systems that supply service water | |||
influenced corrosion in carbon steel piping systems that supply | |||
to emergency diesel generators. | |||
===It is expected that recipients will review=== | |||
the information for applicability to their facilities and consider actions, as | |||
appropriate, to avoid similar problems. However, suggestions contained in | |||
this information notice are not NRC requirements; therefore, no | this information notice are not NRC requirements; therefore, no specific | ||
action or written response is required. | action or written response is required. | ||
| Line 58: | Line 55: | ||
===Haddam Neck Plant=== | ===Haddam Neck Plant=== | ||
On February 12, 1994, a through-wall leak developed in the service water | |||
system supply piping to the "A" emergency diesel generator. The leak occurred | |||
in a weld in an area of low flow, where the licensee was doing light surface | |||
grinding to prepare for ultrasonic test (UT) inspection. | |||
in | ===Previously, in March=== | ||
1993, the licensee had found a similar leak associated with the "B" emergency | |||
diesel generator. After removing the leaking section and examining the pipe, the licensee determined that the leak was caused by poor initial weld quality | |||
and microbiologically influenced corrosion. Lack of penetration of some welds | |||
created a crevice condition. | |||
of | Radiographic tests (RT) of additional emergency | ||
diesel generator service water system piping revealed three additional welds | |||
that could form similar leaks. | |||
that could form similar leaks. | |||
===It was during preparation of one of these=== | |||
welds for UT examination that the through-wall leak associated with the "A" | |||
emergency diesel generator was found. | emergency diesel generator was found. | ||
in | The licensee had previously performed a structural integrity determination in | ||
1993 by radiography. Though based on a uniform wall loss instead of a sharp | |||
,disruption, the licensee had at that time concluded that the worst-case | |||
degraded cross-section of the as-found pipe welds, located in the unisolable | |||
, | portions of the emergency diesel generator supply piping, met the Generic | ||
Letter 90-05 acceptance criteria for structural integrity and that the | |||
degraded piping would have sufficient mechanical and structural integrity to | |||
remain operable. | |||
&_ | |||
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. | |||
in '^* | |||
94170C | |||
9411170039 towzl +2ji | |||
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IN 94-79 November 23, 1994 Beaver Valley Power Station. Unit I | IN 94-79 November 23, 1994 Beaver Valley Power Station. Unit I | ||
| Line 126: | Line 119: | ||
emergency diesel generators. The leak developed on the below-grade portion of | emergency diesel generators. The leak developed on the below-grade portion of | ||
the 15-cm [6-inch] diameter A106 Grade B carbon steel piping. | the 15-cm [6-inch] diameter A106 Grade B carbon steel piping. | ||
===The licensee=== | |||
excavated the "A" and 'B" train headers, ultrasonically examined them using | excavated the "A" and 'B" train headers, ultrasonically examined them using | ||
| Line 134: | Line 128: | ||
than minimum required wall thickness in three additional locations along the | than minimum required wall thickness in three additional locations along the | ||
"A" train piping. The pits were not clustered or closely spaced, but were | "A" train piping. | ||
The pits were not clustered or closely spaced, but were | |||
located along the pipe length between the five and seven o'clock positions. | located along the pipe length between the five and seven o'clock positions. | ||
| Line 144: | Line 140: | ||
The licensee evaluated the pitting in accordance with the American Society of | The licensee evaluated the pitting in accordance with the American Society of | ||
Mechanical Engineers (ASME) Code of record. | Mechanical Engineers (ASME) Code of record. | ||
===The basis for the localized=== | |||
thinning evaluation was conducted in accordance with industry guidance, EPRI | thinning evaluation was conducted in accordance with industry guidance, EPRI | ||
| Line 196: | Line 193: | ||
underneath them for microorganisms, such as sulfate-reducing bacteria, to | underneath them for microorganisms, such as sulfate-reducing bacteria, to | ||
accumulate at the metal surface. | accumulate at the metal surface. | ||
Sulfate-reducing bacteria attack the metal | |||
K>J | surface, produce corrosive chemicals, and cause deep pitting. | ||
K>J | |||
IN 94-79 November 23, 1994 Microbiologically influenced corrosion on carbon steel will increase general | |||
corrosion, through-wall pitting, and the formation of tubercles. Tubercles | corrosion, through-wall pitting, and the formation of tubercles. Tubercles | ||
| Line 242: | Line 243: | ||
corrosion severely damages them or where mitigation measures cannot bring the | corrosion severely damages them or where mitigation measures cannot bring the | ||
system condition under control. | system condition under control. | ||
===Possible alternatives include replacing=== | |||
carbon steel with stainless steel or replacing stainless steel with more | carbon steel with stainless steel or replacing stainless steel with more | ||
| Line 274: | Line 276: | ||
Vv BaD | Vv BaD | ||
D ision f Project Support | ===D ision f Project Support=== | ||
Office of Nuclear Reactor Regulation | |||
Technical contacts: Michael Modes, RI | |||
===James A. Davis, NRR=== | |||
(215) 337-5198 | |||
(301) 504-2713 Peter P. Sena, RI | |||
( | ===Vern Hodge, NRR=== | ||
(412) 643-2000 | |||
(301) 504-1861 Attachment: | |||
===List of Recently ssued NRC Information Notices=== | |||
hi | |||
It6 J'4 | |||
K> | K> | ||
Attachment | |||
IN 94-79 | IN 94-79 | ||
===November 23, 1994 LIST OF RECENTLY ISSUED=== | |||
NRC INFORMATION NOTICES | NRC INFORMATION NOTICES | ||
Information | |||
Date of | |||
Notice No. | |||
Subject | |||
Issuance | |||
Issued to | |||
94-77 | 94-78 | ||
94-77 | |||
94-76 | |||
93-60, | |||
Supp. 1 | |||
94-75 | |||
94-74 | |||
94-73 | |||
94-72 | |||
94-71 | |||
===Electrical Component=== | |||
Failure due to Degrada- tion of Polyvinyl Chloride | |||
===Wire Insulation=== | |||
Malfunction in Main Gen- erator Voltage Regulator | |||
===Causing Overvoltage at=== | |||
Safety-Related Electrical | Safety-Related Electrical | ||
Equipment | Equipment | ||
Recent Failures of Charging/ | |||
===Safety Injection Pump Shafts=== | |||
Reporting Fuel Cycle | |||
and Materials Events to | |||
the NRC Operations Center | |||
===Minimum Temperature=== | |||
for Criticality | |||
===Facility Management=== | |||
Responsibilities for | |||
===Purchased or Contracted=== | |||
Services for Radiation | |||
===Therapy Programs=== | |||
Clarification of Critical- ity Reporting Criteria | |||
===Increased Control Rod=== | |||
Drop Time from Crud | |||
Buildup | |||
===Degradation of Scram=== | |||
Solenoid Pilot Valve | |||
===Pressure and Exhaust=== | |||
Diaphragms | |||
11/21/94 | |||
11/17/94 | |||
10/26/94 | |||
10/20/94 | |||
10/14/94 | |||
10/13/94 | |||
10/12/94 | |||
10/05/94 | |||
10/04/94 | |||
===All holders of OLs or CPs=== | |||
for nuclear power reactors. | |||
===All holders of OLs or CPs=== | |||
for nuclear power reactors. | |||
===All holders of OLs or CPs=== | |||
for pressurized water | |||
reactors. | |||
===All 10 CFR Part 70=== | |||
fuel cycle licensees. | |||
===All holders of OLs or CPs=== | |||
pressurized-water reactors | |||
(PWRs). | |||
===All U.S. Nuclear Regulatory=== | |||
Commission Medical | |||
Licensees. | |||
===All fuel fabrication=== | |||
facilities. | |||
===All holders of OLs or CPs=== | |||
for pressurized water | |||
reactors. | |||
===All holders of OLs or CPs=== | |||
for boiling water reactors | |||
(BWRs). | |||
OL - Operating License | OL - Operating License | ||
| Line 365: | Line 420: | ||
- | - | ||
1/4<> | |||
A~-' | |||
IN 94-79 November 23, 1994 The licensee did not regularly treat the Beaver Valley River water supply | |||
lines to the diesel with biocide or corrosion inhibitors. The chlorination | lines to the diesel with biocide or corrosion inhibitors. The chlorination | ||
| Line 371: | Line 428: | ||
injection point for the main river water headers is downstream of the branch | injection point for the main river water headers is downstream of the branch | ||
lines to the emergency diesel generators. | lines to the emergency diesel generators. | ||
===It also appears that the existing=== | |||
program at Haddam Neck of hypochlorite injection was not successful in | program at Haddam Neck of hypochlorite injection was not successful in | ||
| Line 379: | Line 437: | ||
dead-end lines at such locations as the emergency diesel generator supply. | dead-end lines at such locations as the emergency diesel generator supply. | ||
This information notice requires no specific action or written response. If | This information notice requires no specific action or written response. | ||
If | |||
you have any questions about the information in this notice, please contact | you have any questions about the information in this notice, please contact | ||
| Line 387: | Line 447: | ||
Nuclear Reactor Regulation (NRR) project manager. | Nuclear Reactor Regulation (NRR) project manager. | ||
Original signed by B.D. Liaw for | ===Original signed by B.D. Liaw for=== | ||
Brian K. Grimes, Director | |||
===Division of Project Support=== | |||
Office of Nuclear Reactor Regulation | |||
Technical contacts: | |||
Michael Modes, | |||
(215) 337-5198 RI | |||
===James A. Davis, NRR=== | |||
(301) 504-2713 | |||
===Peter P. Sena, RI=== | |||
(412) 643-2000 | |||
===Vern Hodge, NRR=== | |||
(301) 504-1861 Attachment: | |||
===List of Recently Issued NRC Information Notices=== | |||
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DOCUMENT NAME: | |||
94-79.IN | |||
IN 94-XX | |||
October xx, 1994 inhibitors. | |||
===The chlorination injection point for the main river=== | |||
water headers is downstream of the branch lines to the emergency | |||
diesel generators. | |||
===It also appears that the existing program at=== | |||
Haddam Neck of hypochlorite injection was not successful in | |||
mitigating the microbiologically influenced corrosion problems in | |||
stagnant dead-end lines to such | stagnant dead-end lines to such locations as the emergency diesel | ||
generator supply. | generator supply. | ||
| Line 485: | Line 594: | ||
This information notice requires no specific action or written | This information notice requires no specific action or written | ||
response. | response. | ||
===If you have any questions about the information in=== | |||
this notice, please contact one of the technical contacts listed | this notice, please contact one of the technical contacts listed | ||
| Line 493: | Line 603: | ||
(NRR) project manager. | (NRR) project manager. | ||
Brian K. Grimes, Director | ===Brian K. Grimes, Director=== | ||
Division of Operating Reactor | Division of Operating Reactor | ||
Support | Support | ||
Office of Nuclear Reactor | ===Office of Nuclear Reactor=== | ||
Regulation | Regulation | ||
Technical contacts: | Technical contacts: | ||
(215) 337-5198 | ===Michael Modes, Region I=== | ||
(215) 337-5198 | |||
===Peter P. Sena, Region I=== | |||
(412) 643-2000 | (412) 643-2000 | ||
(301) 504-2713 Attachment: | ===James A.Davis, NRR=== | ||
(301) 504-2713 Attachment: | |||
===List of Recently Issued NRC Information Notices=== | |||
*SEE PREVIOUS CONCURRENCE | *SEE PREVIOUS CONCURRENCE | ||
OFFICE | OFFICE | ||
*OGCB/DORS | |||
*TECH ED | |||
*REGION I | |||
*REGION I | |||
NAME | |||
CVHodge | |||
JDMain | |||
MCModes | |||
PPSena | |||
DATE | |||
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09/01/94 | |||
10/03/94 | |||
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09/20/94 | |||
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10/06/94 | |||
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10/ | |||
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________ | |||
_DOCUMENT NAME: | |||
NECK-MIC. | |||
INY | |||
- | - | ||
IN 94-XX | |||
September xx, | September xx, 1994 stagnant dead-end lines to such locations as the emergency diesel | ||
generator supply. | generator supply. | ||
| Line 545: | Line 722: | ||
This information notice requires no specific action or written | This information notice requires no specific action or written | ||
response. | response. | ||
===If you have any questions about the information in=== | |||
this notice, please contact one of the technical contacts listed | this notice, please contact one of the technical contacts listed | ||
| Line 553: | Line 731: | ||
(NRR) project manager. | (NRR) project manager. | ||
Brian K. Grimes, Director | ===Brian K. Grimes, Director=== | ||
Division of Operating Reactor | Division of Operating Reactor | ||
Support | Support | ||
Office of Nuclear Reactor | ===Office of Nuclear Reactor=== | ||
Regulation | Regulation | ||
Technical contacts: | Technical contacts: | ||
(215) 337-5198 | ===Michael Modes, Region I=== | ||
(215) 337-5198 | |||
===Peter P. Sena, Region I=== | |||
(412) 643-2000 | (412) 643-2000 | ||
(301) 504-2713 Attachment: | ===James A. Davis, NRR=== | ||
(301) 504-2713 Attachment: | |||
===List of Recently Issued NRC Information Notices=== | |||
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| Line 623: | Line 857: | ||
September xx, 1994 This information notice requires no specific action or written | September xx, 1994 This information notice requires no specific action or written | ||
response. | response. | ||
===If you have any questions about the information in=== | |||
this notice, please contact one of the technical contacts listed | this notice, please contact one of the technical contacts listed | ||
| Line 631: | Line 866: | ||
(NRR) project manager. | (NRR) project manager. | ||
Brian K. Grimes, Director | ===Brian K. Grimes, Director=== | ||
Division of Operating Reactor | Division of Operating Reactor | ||
Support | Support | ||
Office of Nuclear Reactor | ===Office of Nuclear Reactor=== | ||
Regulation | Regulation | ||
Technical contacts: | Technical contacts: | ||
(215) 337-5198 | ===Michael Modes, Region I=== | ||
(215) 337-5198 | |||
===Peter P. Sena, Region I=== | |||
(412) 643-2000 | (412) 643-2000 | ||
(301) 504-2713 Attachment: | ===James A. Davis, NRR=== | ||
(301) 504-2713 Attachment: | |||
===List of Recently Issued NRC Information Notices=== | |||
*SEE PREVIOUS CONCURRENCE | |||
--- | |||
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09/01/94 | |||
09/ | |||
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===JRStrosnider=== | |||
09/ | |||
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09/0O/94 | |||
09/7v/94 | |||
09/ | |||
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D:DORS/NRR | |||
BWSheron | |||
ELDoolittle | |||
BKGrimes | |||
09/ | 09/ | ||
/94 | |||
09/ | |||
/94 | |||
09/ | |||
/94 DOCU;MENT NAME: | |||
NECK-MIC.INF}} | |||
{{Information notice-Nav}} | {{Information notice-Nav}} | ||
Latest revision as of 10:49, 16 January 2025
I
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555
November 23, 1994
MICROBIOLOGICALLY INFLUENCED CORROSION OF
EMERGENCY DIESEL GENERATOR SERVICE WATER PIPING
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
PurDose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to degradation resulting from microbiologically
influenced corrosion in carbon steel piping systems that supply service water
to emergency diesel generators.
It is expected that recipients will review
the information for applicability to their facilities and consider actions, as
appropriate, to avoid similar problems. However, suggestions contained in
this information notice are not NRC requirements; therefore, no specific
action or written response is required.
Description of Circumstances
Haddam Neck Plant
On February 12, 1994, a through-wall leak developed in the service water
system supply piping to the "A" emergency diesel generator. The leak occurred
in a weld in an area of low flow, where the licensee was doing light surface
grinding to prepare for ultrasonic test (UT) inspection.
Previously, in March
1993, the licensee had found a similar leak associated with the "B" emergency
diesel generator. After removing the leaking section and examining the pipe, the licensee determined that the leak was caused by poor initial weld quality
and microbiologically influenced corrosion. Lack of penetration of some welds
created a crevice condition.
Radiographic tests (RT) of additional emergency
diesel generator service water system piping revealed three additional welds
that could form similar leaks.
It was during preparation of one of these
welds for UT examination that the through-wall leak associated with the "A"
emergency diesel generator was found.
The licensee had previously performed a structural integrity determination in
1993 by radiography. Though based on a uniform wall loss instead of a sharp
,disruption, the licensee had at that time concluded that the worst-case
degraded cross-section of the as-found pipe welds, located in the unisolable
portions of the emergency diesel generator supply piping, met the Generic
Letter 90-05 acceptance criteria for structural integrity and that the
degraded piping would have sufficient mechanical and structural integrity to
remain operable.
&_
r"
.
in '^*
94170C
9411170039 towzl +2ji
)K I TE NO-rice
H#-14-u1 T4 lII /-
-"5
IN 94-79 November 23, 1994 Beaver Valley Power Station. Unit I
On May 6, 1994, the licensee found a through-wall leak (an 8 mm [5/16 inch]
diameter hole) on the "Al train reactor plant river water system header to the
emergency diesel generators. The leak developed on the below-grade portion of
the 15-cm [6-inch] diameter A106 Grade B carbon steel piping.
The licensee
excavated the "A" and 'B" train headers, ultrasonically examined them using
the "autoscan" area mapping technique, and found localized pitting to less
than minimum required wall thickness in three additional locations along the
"A" train piping.
The pits were not clustered or closely spaced, but were
located along the pipe length between the five and seven o'clock positions.
For reference, the nominal pipe wall thickness is 6.4 mm [0.25 inch] and
minimum code wall thickness is 1.5 mm [0.06 inch].
The licensee evaluated the pitting in accordance with the American Society of
Mechanical Engineers (ASME) Code of record.
The basis for the localized
thinning evaluation was conducted in accordance with industry guidance, EPRI
NP-59IISP, "Acceptance Criteria for Structural Evaluation of Erosion-Corrosion
Thinning in Carbon Steel Piping." This evaluation was reviewed by personnel
in NRR and deemed as an acceptable conservative means of demonstrating ASME
Code conformance. The licensee determined microbiologically influenced
corrosion to be the cause of the pitting and through-wall leak. The licensee
removed a 0.61 m [24 inch] long section of piping to culture and characterize
the microbial activity and perform additional ultrasonic testing.
The general inside surface of the piping was moderately corroded, with
localized pits and tubercles. Cultures from the pits contained sulfur- reducing bacteria and the anaerobic bacteria Clostridium. The tubercle
formation was the result of the growth of the iron-oxidizing bacteria
Gallionella. Ultrasonic examinations of a heat-affected zone indicated that
the weld examined was not subject to preferential microbiologically influenced
corrosion attack.
Discussion
Stagnant or intermittent-flow conditions, as in the case of emergency diesel
service water supply headers, are conducive to the growth of microorganisms
that can accelerate corrosion rates. Service water supply lines to emergency
diesel generators are stagnant because motor-operated isolation valves are
normally maintained shut (except during monthly surveillance testing).
Crevices such as those in piping welds that lack penetration can enhance
microbiologically influenced corrosion attack by giving a place for deposits
and, therefore, for the bacteria to collect. Microbial films form when
aerobic species, such as iron-oxidizing bacteria, create anaerobic conditions
underneath them for microorganisms, such as sulfate-reducing bacteria, to
accumulate at the metal surface.
Sulfate-reducing bacteria attack the metal
surface, produce corrosive chemicals, and cause deep pitting.
K>J
IN 94-79 November 23, 1994 Microbiologically influenced corrosion on carbon steel will increase general
corrosion, through-wall pitting, and the formation of tubercles. Tubercles
consist of corrosion products, microbes, and debris. Tubercle growth could
restrict cooling water flow to equipment.
Stainless steel piping is not immune to microbiologically influenced corrosion
because microbes can attack at the weld heat affected zone (HAZ) in stainless
steels when this zone becomes sensitized. Microbiologically influenced
corrosion can also damage metals lined with polymeric materials, typically at
coating imperfections.
Once microbial films are established on metal surfaces, they are extremely
difficult to eliminate because of the resiliency of the individual
microorganisms. Biocides are applied by some licensees in areas where
continuous flow conditions cannot be maintained. However, biocide treatments
are not always effective against established microorganism colonies because
the biocide cannot penetrate through the tubercles or aerobic biofilms.
Treatment against established colonies involves a combination of mechanical or
chemical pipe cleaning, continued water treatment and regular maintenance.
Continuous flow conditions have been found to prevent the attachment and
growth of microbial films.
It may be necessary to replace materials if microbiologically influenced
corrosion severely damages them or where mitigation measures cannot bring the
system condition under control.
Possible alternatives include replacing
carbon steel with stainless steel or replacing stainless steel with more
resistant materials, such as 6-percent molybdenum stainless steels, nickel
base alloys, titanium, or nonmetallic materials.
The licensee did not regularly treat the Beaver Valley River water supply
lines to the diesel with biocide or corrosion inhibitors. The chlorination
injection point for the main river water headers is downstream of the branch
lines to the emergency diesel generators. It also appears that the existing
program at Haddam Neck of hypochlorite injection was not successful in
mitigating the microbiologically influenced corrosion problems in stagnant
dead-end lines at such locations as the emergency diesel generator supply.
IN 94-79 November 23, 1994 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Vv BaD
D ision f Project Support
Office of Nuclear Reactor Regulation
Technical contacts: Michael Modes, RI
James A. Davis, NRR
(215) 337-5198
(301) 504-2713 Peter P. Sena, RI
Vern Hodge, NRR
(412) 643-2000
(301) 504-1861 Attachment:
List of Recently ssued NRC Information Notices
hi
It6 J'4
K>
Attachment
November 23, 1994 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information
Date of
Notice No.
Subject
Issuance
Issued to
94-78
94-77
94-76
93-60,
Supp. 1
94-75
94-74
94-73
94-72
94-71
Electrical Component
Failure due to Degrada- tion of Polyvinyl Chloride
Wire Insulation
Malfunction in Main Gen- erator Voltage Regulator
Causing Overvoltage at
Safety-Related Electrical
Equipment
Recent Failures of Charging/
Safety Injection Pump Shafts
Reporting Fuel Cycle
and Materials Events to
the NRC Operations Center
Minimum Temperature
for Criticality
Facility Management
Responsibilities for
Purchased or Contracted
Services for Radiation
Therapy Programs
Clarification of Critical- ity Reporting Criteria
Increased Control Rod
Drop Time from Crud
Buildup
Degradation of Scram
Solenoid Pilot Valve
Pressure and Exhaust
11/21/94
11/17/94
10/26/94
10/20/94
10/14/94
10/13/94
10/12/94
10/05/94
10/04/94
All holders of OLs or CPs
for nuclear power reactors.
All holders of OLs or CPs
for nuclear power reactors.
All holders of OLs or CPs
for pressurized water
reactors.
All 10 CFR Part 70
fuel cycle licensees.
All holders of OLs or CPs
pressurized-water reactors
(PWRs).
All U.S. Nuclear Regulatory
Commission Medical
Licensees.
All fuel fabrication
facilities.
All holders of OLs or CPs
for pressurized water
reactors.
All holders of OLs or CPs
for boiling water reactors
(BWRs).
OL - Operating License
CP = Construction Permit
-
1/4<>
A~-'
IN 94-79 November 23, 1994 The licensee did not regularly treat the Beaver Valley River water supply
lines to the diesel with biocide or corrosion inhibitors. The chlorination
injection point for the main river water headers is downstream of the branch
lines to the emergency diesel generators.
It also appears that the existing
program at Haddam Neck of hypochlorite injection was not successful in
mitigating the microbiologically influenced corrosion problems in stagnant
dead-end lines at such locations as the emergency diesel generator supply.
This information notice requires no specific action or written response.
If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Original signed by B.D. Liaw for
Brian K. Grimes, Director
Division of Project Support
Office of Nuclear Reactor Regulation
Technical contacts:
(215) 337-5198 RI
James A. Davis, NRR
(301) 504-2713
Peter P. Sena, RI
(412) 643-2000
Vern Hodge, NRR
(301) 504-1861 Attachment:
List of Recently Issued NRC Information Notices
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October xx, 1994 inhibitors.
The chlorination injection point for the main river
water headers is downstream of the branch lines to the emergency
diesel generators.
It also appears that the existing program at
Haddam Neck of hypochlorite injection was not successful in
mitigating the microbiologically influenced corrosion problems in
stagnant dead-end lines to such locations as the emergency diesel
generator supply.
This information notice requires no specific action or written
response.
If you have any questions about the information in
this notice, please contact one of the technical contacts listed
below or the appropriate Office of Nuclear Reactor Regulation
(NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor
Support
Office of Nuclear Reactor
Regulation
Technical contacts:
Michael Modes, Region I
(215) 337-5198
Peter P. Sena, Region I
(412) 643-2000
James A.Davis, NRR
(301) 504-2713 Attachment:
List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCE
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September xx, 1994 stagnant dead-end lines to such locations as the emergency diesel
generator supply.
This information notice requires no specific action or written
response.
If you have any questions about the information in
this notice, please contact one of the technical contacts listed
below or the appropriate Office of Nuclear Reactor Regulation
(NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor
Support
Office of Nuclear Reactor
Regulation
Technical contacts:
Michael Modes, Region I
(215) 337-5198
Peter P. Sena, Region I
(412) 643-2000
James A. Davis, NRR
(301) 504-2713 Attachment:
List of Recently Issued NRC Information Notices
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September xx, 1994 This information notice requires no specific action or written
response.
If you have any questions about the information in
this notice, please contact one of the technical contacts listed
below or the appropriate Office of Nuclear Reactor Regulation
(NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor
Support
Office of Nuclear Reactor
Regulation
Technical contacts:
Michael Modes, Region I
(215) 337-5198
Peter P. Sena, Region I
(412) 643-2000
James A. Davis, NRR
(301) 504-2713 Attachment:
List of Recently Issued NRC Information Notices
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