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


WASHINGTON, D.C. 20555 November 23, 1994 NRC INFORMATION NOTICE 94-79:   MICROBIOLOGICALLY INFLUENCED CORROSION OF
===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==
power
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


service water
influenced corrosion in carbon steel piping systems that supply service water
 
influenced corrosion in carbon steel piping systems that supply will review
 
to emergency diesel generators. It is expected that recipients          actions, as


the information for applicability to their facilities and consider              in
to emergency diesel generators.


appropriate, to avoid similar problems. However, suggestions      contained
===It is expected that recipients will review===
the information for applicability to their facilities and consider actions, as


specific
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===
                                                                        water
On February 12, 1994, a through-wall leak developed in the service water


On February 12, 1994, a through-wall leak developed in the serviceleak occurred
system supply piping to the "A" emergency diesel generator. The leak occurred


system supply piping to the "A" emergency diesel generator.      The
in a weld in an area of low flow, where the licensee was doing light surface


light surface
grinding to prepare for ultrasonic test (UT) inspection.


in a weld in an area of low flow, where the licensee was doing              in March
===Previously, in March===
1993, the licensee had found a similar leak associated with the "B" emergency


grinding to prepare for ultrasonic test (UT) inspection.     Previously, 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


1993, the licensee had found a similar leak associated                    the pipe, diesel generator. After removing the leaking section and examining    weld  quality
and microbiologically influenced corrosion. Lack of penetration of some welds


the licensee determined that the leak was caused by poor    initial
created a crevice condition.


of some  welds
Radiographic tests (RT) of additional emergency


and microbiologically influenced corrosion. Lack of penetration          emergency
diesel generator service water system piping revealed three additional welds


created a crevice condition. Radiographic tests (RT) of    additional
that could form similar leaks.
 
welds
 
diesel generator service water system piping revealed three additionalof  these
 
that could form similar leaks. It was during preparation    of  one
 
the "A"
welds for UT examination that the through-wall leak associated with


===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


The licensee had previously performed a structural integrity determination
1993 by radiography. Though based on a uniform wall loss instead of a sharp


of  a sharp
,disruption, the licensee had at that time concluded that the worst-case


1993 by radiography. Though based on a uniform wall    loss  instead
degraded cross-section of the as-found pipe welds, located in the unisolable


,disruption, the licensee had at that time concluded that the worst-case unisolable
portions of the emergency diesel generator supply piping, met the Generic


degraded cross-section of the as-found pipe welds, located in the Generic
Letter 90-05 acceptance criteria for structural integrity and that the


portions of the emergency diesel generator supply piping,    met  the
degraded piping would have sufficient mechanical and structural integrity to


that the
remain operable.


Letter 90-05 acceptance criteria for structural integrity and        integrity to
&_
r"
.


degraded piping would have sufficient mechanical and structural
in '^*
94170C


remain operable.            &_                    r"                          .
9411170039 towzl +2ji


in '^*
)K I TE NO-rice
          94170C      )K I TE         NO-rice         H#-14-u1                T4 lII /-
  9411170039 towzl +2ji


-"5
H#-14-u1 T4 lII /-
-"5


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 licensee
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. The basis for the localized
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.   Sulfate-reducing bacteria attack the metal
accumulate at the metal surface.


surface, produce  corrosive chemicals, and cause deep pitting.
Sulfate-reducing bacteria attack the metal


K>J                                     IN 94-79 November 23, 1994 Microbiologically influenced corrosion on carbon steel will increase general
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. Possible alternatives include replacing
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


Office of Nuclear Reactor Regulation
Technical contacts: Michael Modes, RI


Technical contacts:  Michael Modes, RI    James A. Davis, NRR
===James A. Davis, NRR===
(215) 337-5198
(301) 504-2713 Peter P. Sena, RI


(215) 337-5198      (301) 504-2713 Peter P. Sena, RI    Vern Hodge, NRR
===Vern Hodge, NRR===
(412) 643-2000
(301) 504-1861 Attachment:


(412) 643-2000      (301) 504-1861 Attachment:
===List of Recently ssued NRC Information Notices===
hi


===List of Recently===
It6 J'4
hi                  It6       J'4 ssued NRC Information Notices


K>
K>
                                                          Attachment
Attachment


IN 94-79 November 23, 1994 LIST OF RECENTLY ISSUED
IN 94-79


===November 23, 1994 LIST OF RECENTLY ISSUED===
NRC INFORMATION NOTICES
NRC INFORMATION NOTICES


===Information                                 Date of===
Information
Notice No.            Subject                Issuance    Issued to
 
Date of


94-78          Electrical Component          11/21/94    All holders of OLs or CPs
Notice No.


Failure due to Degrada-                    for nuclear power reactors.
Subject


tion of Polyvinyl Chloride
Issuance


Wire Insulation
Issued to


94-77         Malfunction in Main Gen-     11/17/94     All holders of OLs or CPs
94-78
94-77
94-76
93-60,
Supp. 1
94-75
94-74
94-73
94-72
94-71


erator Voltage Regulator                  for nuclear power reactors.
===Electrical Component===
Failure due to Degrada- tion of Polyvinyl Chloride


Causing Overvoltage at
===Wire Insulation===
Malfunction in Main Gen- erator Voltage Regulator


===Causing Overvoltage at===
Safety-Related Electrical
Safety-Related Electrical


Equipment
Equipment


94-76          Recent Failures of Charging/ 10/26/94    All holders of OLs or CPs
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


Safety Injection Pump Shafts              for pressurized water
===Purchased or Contracted===
Services for Radiation


reactors.
===Therapy Programs===
Clarification of Critical- ity Reporting Criteria


93-60,        Reporting Fuel Cycle          10/20/94    All 10 CFR Part 70
===Increased Control Rod===
Supp. 1        and Materials Events to                    fuel cycle licensees.
Drop Time from Crud


the NRC Operations Center
Buildup


94-75          Minimum Temperature          10/14/94    All holders of OLs or CPs
===Degradation of Scram===
Solenoid Pilot Valve


for Criticality                            pressurized-water reactors
===Pressure and Exhaust===
Diaphragms


(PWRs).
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


94-74          Facility Management          10/13/94    All U.S. Nuclear Regulatory
===All holders of OLs or CPs===
for nuclear power reactors.


Responsibilities for                       Commission Medical
===All holders of OLs or CPs===
for nuclear power reactors.


Purchased or Contracted                    Licensees.
===All holders of OLs or CPs===
for pressurized water


Services for Radiation
reactors.


Therapy Programs
===All 10 CFR Part 70===
fuel cycle licensees.


94-73          Clarification of Critical-   10/12/94    All fuel fabrication
===All holders of OLs or CPs===
pressurized-water reactors


ity Reporting Criteria                    facilities.
(PWRs).


94-72          Increased Control Rod        10/05/94    All holders of OLs or CPs
===All U.S. Nuclear Regulatory===
Commission Medical


Drop Time from Crud                        for pressurized water
Licensees.


Buildup                                    reactors.
===All fuel fabrication===
facilities.


94-71          Degradation of Scram          10/04/94    All holders of OLs or CPs
===All holders of OLs or CPs===
for pressurized water


Solenoid Pilot Valve                      for boiling water reactors
reactors.


Pressure and Exhaust                      (BWRs).
===All holders of OLs or CPs===
for boiling water reactors


Diaphragms
(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
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. It also appears that the existing
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


Brian K. Grimes, Director
===James A. Davis, NRR===
(301) 504-2713
 
===Peter P. Sena, RI===
(412) 643-2000


Division of Project Support
===Vern Hodge, NRR===
(301) 504-1861 Attachment:


Office of Nuclear Reactor Regulation
===List of Recently Issued NRC Information Notices===
*err DDrFlVT)
rnCUriRFNrEN


Technical contacts:                Michael Modes, RI            James A. Davis, NRR
OFFICE


(215) 337-5198                (301) 504-2713 Peter P. Sena, RI              Vern Hodge, NRR
*OGCB/DORS


(412) 643-2000                (301) 504-1861 Attachment:          List of Recently Issued NRC Information Notices
*TECH ED


*err DDrFlVT)        rnCUriRFNrEN
*REGION I


OFFICE                    *OGCB/DORS              *TECH ED            *REGION I          *REGION I
*REGION I


NAME
NAME
CVHodge
JDMain
MCModes
PPSena


DATE
DATE


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    *Ann-nfEDrIOTAN


,          *vI
09/08/94
09/09/94
09/01/94
10/03/94
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09/08/94
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ARBlough
 
JADavis
 
RAHermann


09/01/94 I
===JRStrosnider===
10/03/94
09/20/94
09/20/94
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    ARBlough                              JADavis            RAHermann          JRStrosnider


10/03/94                              09/20/94            09/20/94
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BWSheron                   RLDennig                  AEChaffee                G&      I_J1
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      10/06/94                  10/20/94                  10/25/94            1 1ff_/_ 4 Lj
BWSheron


DOCUMENT NAME:            94-79.IN
RLDennig


IN 94-XX
AEChaffee


October xx, 1994 inhibitors.    The chlorination injection point for the main river
G&
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10/06/94
10/20/94
10/25/94
1 1 ff_/_ 4 Lj


water headers is downstream of the branch lines to the emergency
DOCUMENT NAME:
94-79.IN


diesel generators.    It also appears that the existing program at
IN 94-XX


in
October xx, 1994 inhibitors.


Haddam Neck of hypochlorite injection was not successful
===The chlorination injection point for the main river===
water headers is downstream of the branch lines to the emergency


influenced          corrosion      problems  in
diesel generators.


mitigating the microbiologically
===It also appears that the existing program at===
Haddam Neck of hypochlorite injection was not successful in


locations      as      the   emergency    diesel
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.   If you have any questions about the information in
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:     Michael Modes, Region I
Technical contacts:  


(215) 337-5198 Peter P. Sena, Region I
===Michael Modes, Region I===
(215) 337-5198


===Peter P. Sena, Region I===
(412) 643-2000
(412) 643-2000
                        James A.Davis, NRR


(301) 504-2713 Attachment:   List of Recently Issued NRC Information Notices
===James A.Davis, NRR===
(301) 504-2713 Attachment:  


===List of Recently Issued NRC Information Notices===
*SEE PREVIOUS CONCURRENCE
*SEE PREVIOUS CONCURRENCE


OFFICE       *OGCB/DORS     *TECH ED             *REGION I             *REGION I
OFFICE
 
*OGCB/DORS
 
*TECH ED
 
*REGION I
 
*REGION I
 
NAME
 
CVHodge
 
JDMain
 
MCModes
 
PPSena
 
DATE
 
09/08/94 j09/09/94
09/01/94
10/03/94
.
 
_
-11
*Ann:DRA/RFCION I
 
I *EMCB/DE I *S:EMCB/DE I *C:EMCB/DE
 
ARBlough
 
JADavis
 
RAHermann
 
===JRStrosnider===
10/03/94
09/20/94
09/20/94
09
94
-
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-
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*n
 
FOEC
 
6I1QS
 
I C:994A2'OPS I IWS/NRR
 
BWSheron
 
RLW
 
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NAME          CVHodge        JDMain              MCModes                PPSena
af


DATE          09/08/94      j09/09/94              09/01/94              10/03/94
e
                                      .          _                -11
  *Ann:DRA/RFCION I  I *EMCB/DE      I *S:EMCB/DE          I  *C:EMCB/DE


ARBlough              JADavis        RAHermann              JRStrosnider
B


10/03/94              09/20/94        09/20/94              09      94
j
                              -    -                I - I ~'            - 7i


*n  FOEC        6I1QS      I C:994A2'OPS I IWS/NRR
jes


BWSheron      RLW              A      af    e    jB          jes
10/06/94
10/9
1,/94
10/
/94
________
_DOCUMENT NAME:
NECK-MIC.


10/06/94        1,/94
INY
                10/9              10/      /94      ________
_
DOCUMENT NAME:    NECK-MIC.INY


-
-
                                                                  IN 94-XX
IN 94-XX


September xx,     1994 stagnant dead-end lines to such locations as the emergency diesel
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.               If you have any questions about the information in
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:                 Michael Modes, Region I
Technical contacts:


(215) 337-5198 Peter P. Sena, Region I
===Michael Modes, Region I===
(215) 337-5198


===Peter P. Sena, Region I===
(412) 643-2000
(412) 643-2000
                                      James A. Davis, NRR


(301) 504-2713 Attachment:               List of Recently Issued NRC Information Notices
===James A. Davis, NRR===
(301) 504-2713 Attachment:  


*QVV        DPRVUSTnT1    CONCURRENCE                                            .-- "tfA R'lena-
===List of Recently Issued NRC Information Notices===
    - -. -a
.--  
"tf A R'lena-
*QVV


:L:   V - __s_   ___           -r-                                                 - m --
DPRVUSTnT1 CONCURRENCE
    OFFICE
 
-
-.
 
:L:  
-a
 
V
 
-
__s_  
___  
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OFFICE
 
*OGCB/DORS
 
*TECH ED
 
*REGION I
 
REGION I A


NAME
NAME
CVHodge
I JDMain
MCModes
PPSena


DATE
DATE


*OGCB/DORS
j09/08/94
09/09/94
09/01/94 ff /o3/94
_
I
 
.,
._II
 
annlnPq/RFnTON T


CVHodge
*EMCB/DE


j09/08/94 I *TECH ED
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JDMain
C;EMCB/DE fir


09/09/94
-_
                                                                    *REGION I
I___
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MCModes
_
v_
--
ARBlough


09/01/94 REGION I
JADavis


PPSena
===RAHermann LdRStrosnider===
-___
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09/20/94
09/20/94
09/X6/94
1~.1 Dkbz


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                                                      1~.1 Dkbz                    AC:OGCB/DORS          D:DORS/NRR


BW          on        ELDoolittle            BKGrimes
BKGrimes


__/__       /94         09/   /94           09/     /94 DOCUMgNT NAME:               NECK-MIC.1fir
__/__  
/94  
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A-- 016
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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.   If you have any questions about the information in
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:     Michael Modes, Region I
Technical contacts:


(215) 337-5198 Peter P. Sena, Region I
===Michael Modes, Region I===
(215) 337-5198


===Peter P. Sena, Region I===
(412) 643-2000
(412) 643-2000
                          James A. Davis, NRR


(301) 504-2713 Attachment:   List of Recently Issued NRC Information Notices
===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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S:EMCB/DF
 
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*SEE PREVIOUS CONCURRENCE            ---      e
RAHermann


eIml  .Ac>Iveiw62 OFFICE        OGCB/DORS    TECH ED      A    REGION I        REGION I
===JRStrosnider===
09/  
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09/0O/94
09/7v/94
09/
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NAME          CVHodge  k  ^JDMain            MCModes          PPSena
AC:OGCB/DORS


DATE        1 O9/08/94      09/09/94          09/01/94        09/  /94 ADD:DRS/REGION I    EMCB/DE        S:EMCB/DF      C:EMCB/DE
D:DORS/NRR


ARBlough            JADa          RAHermann      JRStrosnider
BWSheron


09/  /94            09/0O/94      09/7v/94        09/      /94 D: DE          AC:OGCB/DORS    D:DORS/NRR
ELDoolittle


BWSheron      ELDoolittle    BKGrimes
BKGrimes


09/   /94     09/ /94       09/     /94 DOCU;MENT NAME:   NECK-MIC.INF}}
09/  
/94  
09/  
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09/  
/94 DOCU;MENT NAME:  
NECK-MIC.INF}}


{{Information notice-Nav}}
{{Information notice-Nav}}

Latest revision as of 10:49, 16 January 2025

Microbiologically Influenced Corrosion of Emergency Diesel Generator Service Water Piping
ML031060426
Person / Time
Site: Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Crane  
Issue date: 11/23/1994
From: Grimes B
Office of Nuclear Reactor Regulation
To:
References
IN-94-079, NUDOCS 9411170039
Download: ML031060426 (9)


I

UNITED STATES

NUCLEAR REGULATORY COMMISSION

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

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.

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94170C

9411170039 towzl +2ji

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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

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K>

Attachment

IN 94-79

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

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

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:

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:

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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 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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IN 94-XX

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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IN 94-XX

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

  • SEE PREVIOUS CONCURRENCE

---

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09/

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09/

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NECK-MIC.INF