Information Notice 1994-79, Microbiologically Influenced Corrosion of Emergency Diesel Generator Service Water Piping: Difference between revisions
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{{#Wiki_filter:I | {{#Wiki_filter:I | ||
UNITED STATES | |||
NUCLEAR REGULATORY COMMISSION | |||
OFFICE OF NUCLEAR REACTOR REGULATION | |||
INFLUENCED | WASHINGTON, D.C. 20555 November 23, 1994 NRC INFORMATION NOTICE 94-79: MICROBIOLOGICALLY INFLUENCED CORROSION OF | ||
EMERGENCY DIESEL GENERATOR SERVICE WATER PIPING | |||
DIESEL GENERATOR | |||
SERVICE WATER PIPING | |||
==Addressees== | ==Addressees== | ||
power | |||
All holders of operating licenses or construction permits for nuclear | |||
reactors. | |||
PurDose | |||
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information | |||
notice to alert addressees to degradation resulting from microbiologically | |||
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 | |||
appropriate, to avoid similar problems. However, suggestions contained | |||
specific | |||
this information notice are not NRC requirements; therefore, no | |||
action or written response is required. | |||
==Description of Circumstances== | |||
===Haddam Neck Plant=== | |||
water | |||
On February 12, 1994, a through-wall leak developed in the serviceleak occurred | |||
system supply piping to the "A" emergency diesel generator. The | |||
light surface | |||
in a weld in an area of low flow, where the licensee was doing in March | |||
to | grinding to prepare for ultrasonic test (UT) inspection. Previously, with the "B" emergency | ||
1993, the licensee had found a similar leak associated the pipe, diesel generator. After removing the leaking section and examining weld quality | |||
the | the licensee determined that the leak was caused by poor initial | ||
of some welds | |||
and microbiologically influenced corrosion. Lack of penetration emergency | |||
created a crevice condition. Radiographic tests (RT) of additional | |||
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 | |||
emergency diesel generator was found. | |||
in | |||
The licensee had previously performed a structural integrity determination | |||
of a sharp | |||
1993 by radiography. Though based on a uniform wall loss instead | |||
,disruption, the licensee had at that time concluded that the worst-case unisolable | |||
of | degraded cross-section of the as-found pipe welds, located in the Generic | ||
portions of the emergency diesel generator supply piping, met the | |||
that the | that the | ||
Letter 90-05 acceptance criteria for structural integrity and integrity to | |||
degraded piping would have sufficient mechanical and structural | |||
remain operable. &_ r" . | |||
in '^* | |||
94170C )K I TE NO-rice H#-14-u1 T4 lII /- | |||
9411170039 towzl +2ji | |||
-"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 | |||
bacteria | 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 | |||
influenced | the weld examined was not subject to preferential microbiologically influenced | ||
corrosion | corrosion attack. | ||
Discussion | |||
Stagnant or intermittent-flow conditions, as in the case of emergency diesel | |||
of | 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 | |||
influenced | 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 | |||
cannot be maintained. | continuous flow conditions cannot be maintained. However, biocide treatments | ||
are not always effective against established microorganism colonies because | |||
are not always effective | |||
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 | |||
or | 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=== | |||
hi It6 J'4 ssued NRC Information Notices | |||
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 Electrical Component 11/21/94 All holders of OLs or CPs | |||
Failure due to Degrada- for nuclear power reactors. | |||
tion of Polyvinyl Chloride | |||
Wire Insulation | |||
of | 94-77 Malfunction in Main Gen- 11/17/94 All holders of OLs or CPs | ||
erator Voltage Regulator for nuclear power reactors. | |||
Causing Overvoltage at | |||
Safety-Related Electrical | |||
Equipment | |||
94-76 Recent Failures of Charging/ 10/26/94 All holders of OLs or CPs | |||
Safety Injection Pump Shafts for pressurized water | |||
reactors. | |||
93-60, Reporting Fuel Cycle 10/20/94 All 10 CFR Part 70 | |||
Supp. 1 and Materials Events to fuel cycle licensees. | |||
the NRC Operations Center | |||
94-75 Minimum Temperature 10/14/94 All holders of OLs or CPs | |||
for Criticality pressurized-water reactors | |||
(PWRs). | |||
94-74 Facility Management 10/13/94 All U.S. Nuclear Regulatory | |||
Responsibilities for Commission Medical | |||
Purchased or Contracted Licensees. | |||
Services for Radiation | |||
Therapy Programs | |||
94-73 Clarification of Critical- 10/12/94 All fuel fabrication | |||
ity Reporting Criteria facilities. | |||
94-72 Increased Control Rod 10/05/94 All holders of OLs or CPs | |||
Drop Time from Crud for pressurized water | |||
Buildup reactors. | |||
94-71 Degradation of Scram 10/04/94 All holders of OLs or CPs | |||
Solenoid Pilot Valve for boiling water reactors | |||
Pressure and Exhaust (BWRs). | |||
Diaphragms | |||
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 | |||
or | 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 | |||
of | 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 Issued NRC Information Notices | |||
*err DDrFlVT) rnCUriRFNrEN | |||
OFFICE *OGCB/DORS *TECH ED *REGION I *REGION I | |||
NAME | |||
DATE | |||
__ _ | |||
*Ann-nfEDrIOTAN | |||
, *vI | |||
__ _ | |||
J_ | |||
-EI | |||
CVHodge | |||
09/08/94 | |||
_ | |||
T | |||
, | |||
_ | |||
II | |||
* FMrR/nF | |||
JDMain | |||
09/09/94 vv.1,EI__ | |||
*S:EMCB/DE | |||
- - | |||
MCModes | |||
09/01/94 I | |||
*C: EMCB/DE | |||
PPSena | |||
__ | |||
10/03/94 If_ | |||
ARBlough JADavis RAHermann JRStrosnider | |||
10/03/94 09/20/94 09/20/94 | |||
-~~~ II f | |||
*n. _. nr | |||
v.LvL *nCrRR /nnP5 - | |||
I *C AFCBIDOPS I D:DdPWi/Or | |||
BWSheron RLDennig AEChaffee G& I_J1 | |||
10/06/94 10/20/94 10/25/94 1 1ff_/_ 4 Lj | |||
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 | |||
in | |||
Haddam Neck of hypochlorite injection was not successful | |||
in | influenced corrosion problems in | ||
mitigating the microbiologically | |||
locations as the emergency diesel | |||
stagnant dead-end lines to such | |||
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 | |||
of | (301) 504-2713 Attachment: List of Recently Issued NRC Information Notices | ||
*SEE PREVIOUS CONCURRENCE | |||
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 | |||
- - I - I ~' - 7i | |||
*n FOEC 6I1QS I C:994A2'OPS I IWS/NRR | |||
BWSheron RLW A af e jB jes | |||
10/06/94 1,/94 | |||
10/9 10/ /94 ________ | |||
_ | |||
DOCUMENT NAME: NECK-MIC.INY | |||
- | |||
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 | |||
about the information | 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 | |||
I | Technical contacts: Michael Modes, Region I | ||
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 | |||
*QVV DPRVUSTnT1 CONCURRENCE .-- "tfA R'lena- | |||
- -. -a | |||
:L: V - __s_ ___ -r- - m -- | |||
OFFICE | |||
NAME | |||
DATE | |||
*OGCB/DORS | |||
CVHodge | |||
j09/08/94 I *TECH ED | |||
JDMain | |||
09/09/94 | |||
*REGION I | |||
MCModes | |||
09/01/94 REGION I | |||
PPSena | |||
ff /o3/94 A | |||
_ I ., ._II | |||
annlnPq/RFnTON T *EMCB/DE *S: EMCB/DE C;EMCB/DE fir | |||
-_ I___ v_ __a _ -- | |||
ARBlough JADavis RAHermann LdRStrosnider | |||
- | -___ /9 09/20/94 09/20/94 09/X6/94 | ||
1~.1 Dkbz AC:OGCB/DORS D:DORS/NRR | |||
BW on ELDoolittle BKGrimes | |||
__/__ /94 09/ /94 09/ /94 DOCUMgNT NAME: NECK-MIC.1fir | |||
A-- 016 | |||
I | |||
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 | |||
Technical | |||
(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 --- e | |||
TECH ED A REGION I REGION I | eIml .Ac>Iveiw62 OFFICE OGCB/DORS TECH ED A REGION I REGION I | ||
NAME CVHodge k ^JDMain MCModes PPSena | |||
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 | |||
ARBlough JADa RAHermann JRStrosnider | |||
09/ /94 09/0O/94 09/7v/94 09/ /94 D: DE AC:OGCB/DORS D:DORS/NRR | |||
BKGrimes | BWSheron ELDoolittle BKGrimes | ||
NAME: NECK-MIC.INF}} | 09/ /94 09/ /94 09/ /94 DOCU;MENT NAME: NECK-MIC.INF}} | ||
{{Information notice-Nav}} | {{Information notice-Nav}} | ||
Revision as of 03:29, 24 November 2019
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
power
All holders of operating licenses or construction permits for nuclear
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 will review
to emergency diesel generators. It is expected that recipients actions, as
the information for applicability to their facilities and consider in
appropriate, to avoid similar problems. However, suggestions contained
specific
this information notice are not NRC requirements; therefore, no
action or written response is required.
Description of Circumstances
Haddam Neck Plant
water
On February 12, 1994, a through-wall leak developed in the serviceleak occurred
system supply piping to the "A" emergency diesel generator. The
light surface
in a weld in an area of low flow, where the licensee was doing in March
grinding to prepare for ultrasonic test (UT) inspection. Previously, with the "B" emergency
1993, the licensee had found a similar leak associated the pipe, diesel generator. After removing the leaking section and examining weld quality
the licensee determined that the leak was caused by poor initial
of some welds
and microbiologically influenced corrosion. Lack of penetration emergency
created a crevice condition. Radiographic tests (RT) of additional
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
emergency diesel generator was found.
in
The licensee had previously performed a structural integrity determination
of a sharp
1993 by radiography. Though based on a uniform wall loss instead
,disruption, the licensee had at that time concluded that the worst-case unisolable
degraded cross-section of the as-found pipe welds, located in the Generic
portions of the emergency diesel generator supply piping, met the
that the
Letter 90-05 acceptance criteria for structural integrity and integrity to
degraded piping would have sufficient mechanical and structural
remain operable. &_ r" .
in '^*
94170C )K I TE NO-rice H#-14-u1 T4 lII /-
9411170039 towzl +2ji
-"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
hi It6 J'4 ssued NRC Information Notices
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 Electrical Component 11/21/94 All holders of OLs or CPs
Failure due to Degrada- for nuclear power reactors.
tion of Polyvinyl Chloride
Wire Insulation
94-77 Malfunction in Main Gen- 11/17/94 All holders of OLs or CPs
erator Voltage Regulator for nuclear power reactors.
Causing Overvoltage at
Safety-Related Electrical
Equipment
94-76 Recent Failures of Charging/ 10/26/94 All holders of OLs or CPs
Safety Injection Pump Shafts for pressurized water
reactors.
93-60, Reporting Fuel Cycle 10/20/94 All 10 CFR Part 70
Supp. 1 and Materials Events to fuel cycle licensees.
the NRC Operations Center
94-75 Minimum Temperature 10/14/94 All holders of OLs or CPs
for Criticality pressurized-water reactors
(PWRs).
94-74 Facility Management 10/13/94 All U.S. Nuclear Regulatory
Responsibilities for Commission Medical
Purchased or Contracted Licensees.
Services for Radiation
Therapy Programs
94-73 Clarification of Critical- 10/12/94 All fuel fabrication
ity Reporting Criteria facilities.
94-72 Increased Control Rod 10/05/94 All holders of OLs or CPs
Drop Time from Crud for pressurized water
Buildup reactors.
94-71 Degradation of Scram 10/04/94 All holders of OLs or CPs
Solenoid Pilot Valve for boiling water reactors
Pressure and Exhaust (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, 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 Issued NRC Information Notices
- err DDrFlVT) rnCUriRFNrEN
OFFICE *OGCB/DORS *TECH ED *REGION I *REGION I
NAME
DATE
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- Ann-nfEDrIOTAN
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CVHodge
09/08/94
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09/09/94 vv.1,EI__
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- -
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09/01/94 I
- C: EMCB/DE
PPSena
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10/03/94 If_
ARBlough JADavis RAHermann JRStrosnider
10/03/94 09/20/94 09/20/94
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v.LvL *nCrRR /nnP5 -
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BWSheron RLDennig AEChaffee G& I_J1
10/06/94 10/20/94 10/25/94 1 1ff_/_ 4 Lj
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
in
Haddam Neck of hypochlorite injection was not successful
influenced corrosion problems in
mitigating the microbiologically
locations as the emergency diesel
stagnant dead-end lines to such
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
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
- - I - I ~' - 7i
- n FOEC 6I1QS I C:994A2'OPS I IWS/NRR
BWSheron RLW A af e jB jes
10/06/94 1,/94
10/9 10/ /94 ________
_
DOCUMENT NAME: NECK-MIC.INY
-
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
- QVV DPRVUSTnT1 CONCURRENCE .-- "tfA R'lena-
- -. -a
- L: V - __s_ ___ -r- - m --
OFFICE
NAME
DATE
- OGCB/DORS
CVHodge
j09/08/94 I *TECH ED
JDMain
09/09/94
- REGION I
MCModes
09/01/94 REGION I
PPSena
ff /o3/94 A
_ I ., ._II
annlnPq/RFnTON T *EMCB/DE *S: EMCB/DE C;EMCB/DE fir
-_ I___ v_ __a _ --
ARBlough JADavis RAHermann LdRStrosnider
-___ /9 09/20/94 09/20/94 09/X6/94
1~.1 Dkbz AC:OGCB/DORS D:DORS/NRR
BW on ELDoolittle BKGrimes
__/__ /94 09/ /94 09/ /94 DOCUMgNT NAME: NECK-MIC.1fir
A-- 016
I
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 --- e
eIml .Ac>Iveiw62 OFFICE OGCB/DORS TECH ED A REGION I REGION I
NAME CVHodge k ^JDMain MCModes PPSena
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
ARBlough JADa RAHermann JRStrosnider
09/ /94 09/0O/94 09/7v/94 09/ /94 D: DE AC:OGCB/DORS D:DORS/NRR
BWSheron ELDoolittle BKGrimes
09/ /94 09/ /94 09/ /94 DOCU;MENT NAME: NECK-MIC.INF