ML20033F079
| ML20033F079 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 03/08/1990 |
| From: | Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| REF-PT21-90 NYN-90056, NUDOCS 9003150447 | |
| Download: ML20033F079 (17) | |
Text
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- New Hampshire Ted C. F:.. z< zm Senior Vice President and 4
Chief Operating OHicer NYN-90056 March 8, 1990
' United States Nuclear Regulatory Commission Washington, DC 20555
. Attention: ' Document Control Desk
References:
(a)
Facility Operating License No. NPF-67, Docket No. 50-443 (b)
.USNRC Letter dated January 29, 1990, ' Proposed NRC Bulletin on Loss of Fill-Oil in Rosemount Transmitters'. C.H.
Berlinger to NUMARC L
Subject:
Response to Proposed Draft NRC Bulletin on Loss of Fill Oil in Rosemount Transmitters Gentlemen:
During recent discussions with the NRC Staff New Hampshire Yankee (NHY) was requested to provide a response to the proposed draft bulletin on loss of fill-
' oil in Rosemount transmitters. Accordingly enclosed please find NHY's response to the Requested Actions.and Reporting Requirements for Operating Reactors
[ Enclosures 1 and-2 respectively) of the' proposed draft bulletin transmitted via Reference (b).
It is NHY's understanding that the NRC intends to formally issue a bulletin concerning the loss of fill-oil in Rosemounts transmitters in the near
-future..When that bulletin is issued, NHY will respond to it in full. It will
-incorporate where applicable, the enclosed information.
New Hampshire Yankee has been following the Rosemount transmitter fill-oil loss issue closely and has-taken a proactive roll in dealing with the issue. NHY has performed an extensive review of identified Rosemount and identified original equipment manufacturers (OEM) transmitters in addressing the concerns of the proposed draft bulletin. As a result of this review, NHY has concluded that there are aq Rosemount 1152 transmitters there are np,Rosemount Model 1151 transmitter performing safety-related or ATWS related functions and that there are ng. OEM transmitters, containing Rosemount sensing modules of concern, performing safety-related or ATWS related functions. NHY has identified 61 Model 1153 and 1154 Rosemount transmitters which are installed in safety-related L
applications.
a.'
1 NHY has determined that there is only one transmitter installed at Seabrook Station from the Model 1153 and 1154 manufacturing lots identified by O'
Rosemount as having a high failure fraction.
This transmitter is not utilized in N
the reactor protection system (RPS) or engineered safety actuation features f
systems (ESFAS). This transmitter has been installed and in-service for over 3 in g 1/2 years. It has been operating satisfactorily and has not exhibited any symptoms _of potential fill-oil loss. Although not required to be addressed by lp -
the draft bulletin, the spare transmitters which were from the lots with a high n.O failure fraction have-been returned to Rosemount for the replacement of the sensing module.
New Hampshire Yankee Division of Public Service Company of New Hampshire k
P.O. Box 300
- Seabrook, NH 03874
- Telephone (603) 474 9521 h
i United Statos Nucle:r Regulotery Conmission March 8, 1990 Atttntions-Document Control'Dask Page 2 I
A's indicated in the enclosure the calibration data reviews are being performed for all the identified transmitters. The reviews for all transmitters l
utilized in the RPS or ESFAS have been completed.
The conclusions from these reviews are that there are no transmitters identified which have a confirmed l
fill-oil loss of failure or did not meet the established operability acceptance criteria. As indicated in the enclosures, one transmitter has exhibited early symptoms of potential fill-oil loss and is being evaluated in accordance with our program.
New Hampshire Yankee, based on Rosemount's technical bulletins, has developed and implemented a program for detecting the onset of fill-oil loss in Rosemount transmitters before they could lose the ability to perform their safety functions.
The elements of this program include enhanced monitoring of the identified transmitters, trending of transmitter performance, and the action to be taken for a potential fill-oil loss condition.
Should you have any questions regarding the enclosed, please contact Mr.
Terry L. Harpster at (603) 474-9521, extension 2765.
Very truly yours,
.Q(,qh &b^
Ted C. Feigenbaum cci Mr. William T. Russell Regional Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia PA 19406 Mr. Victor Nerses, Project Manager Project Directorate I-3 United States Nuclear Regulatory Commission Division of Reactor Projects Washington, DC 20555 Mr. Noel Dudley NRC Senior Resident Inspector P.O. Box 1149 Seabrook, NH 03874 Atomic Safety and Licensing Board Service List
S.
ASLB SERVICE LIST
)
. Alan S. Rosenthal,' Chairman-Adjudicatory File q
Atomic Safety and Licensing Atomic Safety and Licensing j
-Appeal Panel Board Panel Docket (2 copies)
U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, DC 20555-Washington, DC 20555 Thomas S. Moore Philip Ahrens Esquire
]
Atomic Safety and Licensing Assistant. Attorney General Appeal Panel Officeaof the Attorney General U.S. Nuclear Regulatory Commission
. State House Station #6 Washington,'DC 20555' Augusta, ME 04333 Howard A. Wilber Ashod N. Amirlan, Esquire Atomic Safety and Licensing Assistant City Solicitor Appeal Panel City of Haverhill U.S. Nuclear Regulatory Commission Haverhill, MA 01830 Washington, DC 20555 Robert A. Backus, Esquire G. Paul Bollwerk. III, Chairman Backus, Meyer & Solomon Atomic Safety'and Licensing 116 Lowell Street Appeal Panel P.O. Box 516 L
U.S. Nuclear Regulatory Commission Manchester, NH 03105 Washington, DC 20555 George Dana Bisbee, Esquire Atomic Safety and Licensing Assistant Attorney General Appeals Board Panel
-Office of the Attorney General U.S. Nuclear Regulatory Commission 25 Capitol Street Washington, DC 20555 Concord, NH. 03301-66397 Ivan W. Smith, Chairman Diane Curran, Esquire 1 Atomic Safety and Licensing Board Andrea C. Ferster, Esquire Panel Harmon, Curran & Tousley U.S. Nuclear Regulatory Commission 2001 S Street, N.W.'
Suite 430
. Washington, DC 20555-Washington, DC 20009-1125 Robert R. Pierce, Esquire-Mr. Jack Dolan
-Atomic Safety and Licensing Board Federal Emergency Management Agency Panel Region I
'U.S. Nuclear Regulatory Commission J. W. McCormack Post Office &
Washington, DC 20555 Courthouse Building, Room 442 Boston, MA- 02109 Admin. Judge Kenneth A. McCollom, Member Mr. Richard R. Donovan 1107: West Knapp Street Federal Emergency Management Agency Stillwater, OK 74075 Federal Regional Center 130 228th Street, S.W.
Richard F. Cole Bothell, Washington 98021-9796 Atomic Safety and Licensing Board Panel
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U.S. Nuclear Regulatory Commission Washington, DC 20555
e l
- c V
ASLB SERVICE LIST Judith H. Mizner, Esquire Suzanne P..Egan, City Solicitor 79 State Street,-
Lagoulis, Hill-Whilton'&
Second Floor j
& Rotondi Newburyport, MA. 01950 79 Shate Street Newburyport, MA- 01950 Barbara J. Saint-Andre. Esquire
-H. Joseph Flynn, Esquire Kopelman and Paige, P.C.
77 Franklin Street Office of General Counsel Boston, MA 02110
. Federal Emergency. Management Agency 500 C Street, SW John Traficonte, Esquire
- Washington,jDC 20472 Assistant Attorney General Office of the Attorney General R. Scott Hill-Whilton, Esquire One Ashburton Place, 19th Floor Lagoulis, Clark, Hill-Whilton Boston, MA 02108
& Rotondi 79 State Street Mitzi A Young, Esquire-Newburyport, MA 01950 Edwin J. Reis. Esquire Office of General Counsel.
Gary W.' Holmes, Esquire U.S. Nuclear Regulatory Commission Holmes & Ells
.47 Winnacunnet Road
-Washington, DC 20555 Hampton, NH 03842 Senator Gordon J. Humphrey*
United States Senate Washington, DC 20510 Attention: Tom Burack Senator Gordon J.-Humphrey*
l' Eagle Square, Suite 507
-Concord, NH 03301 Attention: Mary Jane Colton George Iverson, Director N.H. Office of Emergency Management State House Office Park South
-107 Pleasant Street Concord, NH 03301 Paul'McEachern, Esquire Matthew T. Brock, Esquire Shaines & McEachern 25 Maplewood Avenue, P.O. Box 360 Portsmouth, NH 03801
- letter only l
i N:w H:mpshire Y:nkse March 8, 1990 4
1,.
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ENCLOSURE 1 TO NYN-90056' ProDosed Draft Bulletin on Loss of Fill-Oli in Rosemount Transmitters Resoonse to Reauested Actions:
Ooeratinn Reactors L
I l
l' 1.
x
NIw H:mpshirs Ycnkse i
March 8, 1990 4
a Proposed Draft Bulletin on Loss of Fill-Oil in Rosemount Transmitters Resoonse to Reauested Actions:
Operatina Reactors NRC Reauested Action il Identify, within 60 days after the receipt of this bulletin, all pressure or differential pressure transmitters, including Model 1131, 1152, 1153, and 1154 transmitters but excluding Model 1153 and-1154 transmitters manufactured by Rosemount subsequent to July 11, 1989, that were manufactured by Rosemount or that contain Rosemount manufactured sensing modules and are utilized in either safety-related systems or systems installed in accordance with 10 CFR 50.62 (the ATWS rule). Addressees may find it necessary to perform, in addition to document reviews, system walkdowns to complete this action.
[Noten-In addition to the above, the proposed draft bulletin provided additional information to facilitate addressing the above..This additional information has not been repeated herein.)
l NHY Response I
l In regards to Rosemount Model 1151 and 1152 transmitters, there are no Model 1152 transmitters installed at Seabrook Station and there are p31 Model 1151 transmitters at Seabrook Station which perform a safety-related or ATWS related functions.
There are Rosemount Model 1153 and 1154 transmitters at Seabrook Station which perform safety-related functions.
These transmitters are identified on Table 1.
i A review was undertaken to determine if the original equipment manufacturer's l
(OEM's), identified in the proposed draft bulletin, had provided transmitters to Seabrook Station which, as described in the draft bulletin, may have been manufactured by Rosemount or contained a-sensing module manufactured by Rosemount.
The review concluded that only Bailey Controls had supplied I
transmitters to Seabrook Station which utilized a Model 1151 transmitter sensing module. These transmitters do not perform a safety-related or ATWS related function.
NRC Reauested Action #2 l=
Review within 90 days after receipt of this bulletin, plant records (for example, calibration records) associated with the transmitters identified in Item 1 above to determine whether any of these transmitters may have already exhibited symptoms indicative of loss of fill-oil. Appropriate operability acceptance criteria should be developed and applied to transmitters identified as having exhibited symptome indicative of loss of fill-oil from this plant record review.
Transmitters identified as having exhibited symptoms indicative of loss of fill-oil that do not conform to the operability acceptance criteria should be addressed in accordance with the applicable technical specification.
Transmitters identified as having exhibited symptoms indicative of loss of fill-I oil and are not addressed in the technical specifications should be replaced at the earliest appropriate opportunity.
NHY Response As indicated in NHY's response to Action #1 above, the response to this action item need only address the Model 1153 and 1154 Rosemount transmitters identified in Table 1.
The review of plant records (calibration records) associated with the identified model 1153 and 1154 transmitters is presently underway to
.c Ntw H:mpshiro Yankso.
Nkrch 8, 1990 NHY Response *
. determine if they are exhibiting the symptoms of oil leakage. A review has been performed for the calibrations of the Rosemount model 1153 and 1154 transmitters performed between January.1987 to March 1, 1990.
This review included all transmitters utilized in the reactor protection system (RPS) and engineered safety features actuation system (ESPAS) as identified in the Technical Specifications. The results of this review are provided in Enclosure 2 Requirement 1(b).
For calibrations performed between March 1, 1990 and March 9, 1990, the reviews are expected to be completed by March 14, 1990.
This
.will complete calibrations and associated reviews of all the safety-related Model 1153 and 1154 transmitters installed at Seabrook Station.
The method of review utilizes the guidelines of Rosemount Technical Bulletin $4 Appendix A Section 3.. This technical bulletin and its guidance was developed
+
from the extensive testing and evaluation performed by Rosemount in regards to the fill-oil leakage issue. This guidance is utilized to determine if there is a possible fill-oil leak.
If this condition potentially exists then the guidance is used to determine leakage rates and the amount of time in service before significantly degraded performance could be expected. If this review indicates a trend in performance which may be indicative of loss of fill-oil condition then the transmitter will be identified as requiring special attention. A transmitter requiring special attention will be recalibrated before the calculated time in service, based on Rosemount Technical Bulletin f4, that the transmitter response could become degraded.
If that calibration confirms a negative performance trend is continuing, the transmitter will be tested against the operability acceptance criteria.
i For example if the review indicates that the transmitter potential leakage rate l
is such that there should be nine months before the response time might be degraded, the transmitter will be recalibrated in 6 months. The operability acceptance criteria that will be used for any transmitter exhibiting the symptoms indicative of loss of fill oil, is taken from Technical Bulletin f4 Appendix B Section 2 and 3, and is as follows:
Apply a pressure transient of the full range of the transmitter to test the l
time response of the side of the DP cell which is suspected of leaking.
For l
range Code 5-9 the transmitter should respond (or follow since the pressure L
change may be a fast ramp) to this pressure change within 1 second. Range code 3 should respond within 35 seconds and range code 4 should respond l
within 6 seconds.
l Transmitters identified as having exhibited symptoms indicative of loss of fill-oil will be addressed in accordance with the applicable Technical Specification.
Transmitters identified as having exhibited symptoms indicative of loss of fill-oil that do not conform to the operability acceptance criteria and are not addressed in the Technical Specifications will be replaced at the earliest appropriate opportunity.
[
NRC Reauested Action #3 Develop and implement, within 120 days after receipt of this bulletin, an l
enhanced surveillance program to monitor transmitters identified in item 1 for l
symptoms of loss of fill-oil.
This enhanced surveillance program should consider I
the following or equally effective actions:
NIw H:rpshiro Yank 30
= '
hkrch 8 1990 NRC Reauested Action #3 a)
Ensuring appropriate licensee personnel are aware of the symptoms that a transmitter, both during operation and during calibration activities, may.
exhibit if it is experiencing a loss of fill-oil and the need for prompt identification of transmitters that may exhibit these symptoms:
b)
Enhanced transmitter monitoring to identify excessive transmitter drift:
c)
Review of transmitter output data following planned or unplanned plant transients or tests-to identify sluggish transmitter responses d)
Inclusion of sensor response time testing into routine channel calibration i
activities:
e).
Development and implementation of a program to detect a decrease in transmitter noise level amplitudes and f)-
Development and application to transmitters identified as having exhibited symptoms indicative of loss of fill-oil of an appropriate operability acceptance criteria. Transmitters identified as having exhibited symptoms indicative of loss of fill-oil that do not conform to the operability.
acceptance criteria should be addressed in accordance with the applicable technical specification.
Transmitters identified as having exhibited symptoms indicative of loss of fill-oil that do not conform to the operability acceptance criteria and are not addressed in the technical specifications should be replaced at the oarliest appropriate opportunity.
NHY Response The enhanced surveillance program for.the installed Rosemount transmitters is presently being implemented.
This program addresses the considerations of the draft NRC Bulletin as follows:
a)
I&C personnel are aware of the symptoms that a transmitter, both during operation and during calibration activities, may exhibit if it is experiencing a loss of fill-oil.
I&C Department personnel have been on distribution for all pertinent information pertaining to Rosemount Technical Bulletins.and this information has been included into the required reading program in the I&C Department.
In addition, the training department will be scheduling formalized training of operations and I&C personnel regarding.the above over the next 4 months.
b)
The enhanced monitoring program consists of monthly channel checks of the-transmitters identified in Table 1, performed by IEC personnel, and the scheduling of additional calibrations for a transmitter identified as requiring special attention, as discussed in Action #2 above. Channel checks are performed on a monthly basis to determine if any of these transmitters are experiencing a zero or span shift which is the first indication of a possible fill-oil loss.
In the performance of these channel l
checks readings will be taken using either the main plant computer or test equipment to achieve a higher accuracy than can be achieved using panel
. meters.
'd New H:mpshiro Y nkte Nkrch 8, 1990 NHY Response
- c)
Based on the information from Rosemount, monitoring for drift should give the first indication of failure long before the sluggish response due to a transient would be identified.
In addition, the main plant computer system does not have the capability to provide a fast enough scan rate to give meaningful data following unplanned transients to identify the early onset of response time degradation due to fill-oil leakage.
Therefore this method' has not been included in the Station's trending program, d)
The IEC technicians have been made aware to observe for sluggish response when calibrating Rosemount transmitters.
The information from Rosemount indicates that the response will be degraded to such an extent that a formal.
~
response time test on a routine basis will not be required.
However, a time response test will be performed to verify operability of any transmitter Identified by the trending program to have a potential fill-oil loss, e)
The primary method of detection of a potential loss of oil in a sansing module will be the trending of the performance of the instrument channel that is the zero and span shift' observed during the monthly channel checks and the calibrations. Based on the information from Rosemount, monitoring for zero and span shift should give the first indication'of failure before a decrease in transmitter noise level of amplitude would be identified.
Therefore, the noise level amplitude method has not be included in the Station's trending program.
The operability acceptance criteria is as identified in the response to f) _
Action #2 above.
For the actions to be taken for transmitters which do not meet the acceptance criteria see the response to Action #2 above.
NRC Requested Action #4 Determine, within 60 days after receipt of this bulletin, whether any Model 1153 and 1154 transmitters identified in Item 1 are from the manufacturing lots that have been identified by Rosemount as having a high failure fraction due to loss of fill-oil.
(Information concerning these transmitters was provided to industry by Rosemount concurrent with Reference 4).
Addressees are requested not to utilize transmitters from these suspect lots in the reactor protection or engineered safety features actuation systems: therefore, transmitters from these suspect lots in use in the reactor protection or engineered safety features i
actuation systems should be replaced at the earliest appropriate opportunity.
NHY Response There is only one installed 1153 or 1154 transmitter from one of the high failure fraction lots identified by Rosemount at Seabrook Station.
This transmitter monitors EFW suction pressure transmitter which is used in a RG 1.97 Category 1 indicating loop to monitor Condensate Storage Tank Level.
It is not used for Reactor Protection System (RPS) or Engineered Safety Features Actuation System (ESFAS). This transmitter is in a low pressure application and has been in service for over 3 years. After the issuance of the 10CFR21 notification, it was calibrated in May 1989 and again in Dec 1989 and was determined to be operating satisfactorily and has not exhibited any symptoms of potential fill-oil loss.
N3w H:mpshira Y0nke3 Farch 8, 1990 NRC Reauested Action #5 Document, within 60 days after receipt of this bulletin, and maintain in accordance with plant procedures a basis for continued plant operation covering the time period from the present until such time that the Model 1153 and 1154 transmitters from the manufacturing lots that have been identified by Rosemount as having a high failure fraction due to loss of fill-oil in use in the reactor protection or engineered safety features actuation systems can be replaced.
In addition, while performing the actions requested above, addressees may identify transmitters exhibiting symptoms indicative of loss of fill-oil that do not conform to the established operability acceptance criteria and are not addressed in the technical specifications. As these transmitters are identified, this basis for continued plant operation should be updrted to address these transmitters covering the time period from the time these transmitters are identified until such time that these transmitters can be replaced. When developing and updating this basis for continued plant operation, addressees may which to consider transmitter diversity and redundancy, diverse trip functions (a separate trip function that may also provide a corresponding trip signal),
special system and/or component tests, or (if necessary) immediate replacement of certain suspect transmitters.
NHY Response As provided in paragraph 4 above there are no 1153 or 1154 transmitters from the manufacturing lots that have been identified by Rosemount as having a high failure fraction due to loss of fill oil used in the RPS or ESFAS. As also indicated in Enclosure 2 in the Response to Requirement #1(b), there are no transmitters identified which have a confirmed fill-oil loss failure or do not meet the established operability acceptance criteria. Calibration of all the Rosemount 1153 and 1154 transmitters identified on Table 1 was begun in November, 1989 and is expected to.be completed by March 10, 1990 (i.e. an approximately 4 1/2 month period).
Therefore, basis for continued plant operation at Seabrook Station is not required at this time.
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New Hhmpshira Ycnk33 1
March 8, 1990 TABLE 1 j
SAFETY-RELATED ROSEMOUNT TRANSMITTERS Ti TRANSMITTER FUNCTION' MODEL NO.
CC-FT-2091-1 RCP Coolers Outlet Flow Loop A 1153DD3 (Pump Coastdown Protection)
CC-FT-2091-2 RCP Coolers Outlet Flow Loop A 1153DD3
.(Pump Coastdown Protection)
CC-FT-2291-1 RCP Coolers Outlet Flow Loop B 1153DD3 (Pump Coastdown Protection)
CC-FT-2291-2 RCP Coolers Outlet Flow Loop B 1153DD3 (Pump Coastdown Protection)
CC-FT-2175A RCP TB Outlet FR P-322A & B 1153DD5 Thermal Barrier Cooling (Pump Start'1E Interface)
CC-FT-2175B RCP TB Outlet FR P-322A & B 1153DD5 Thermal Barrier Cooling (Pump Start 1E Interface)
CC-LT-2172-1 PCCW Head Tank 19A Level (NNS Header 1153DB4 Isolation Signal)
CC-LT-2172-2 PCCW Head Tank 19A Level (NNS Header 1153DB4 Isolation Signal)
CC-LT-2172-3 PCCW Head Tank 19A Level (NNS Header 1153DB4 Isolation Signal) i CC-LT-2192-1 PCCW Head Tank 19A Level (NNS Header 1153DB4 Isolation Signal)
CC-LT-2192-2 PCCW Head Tank 19A Level (NNS Header 1153DB4 Isolation Signal).
CC-LT-2192-3 PCCW Head Tank 19A Level (NNS Header 1153DB4 Isolation Signal)
CC-LT-2272-1 PCCW Head Tank 19B Level (NNS Header 1153DB4' p
Isolation Signal)
CC-LT-2272-2 PCCW Head Tank 19B Level (NNS Header 1153DB4 Isolation Signal)
CC-LT-2272-3 PCCW Head Tank 19B Level (NNS Header 1153DB4 Isolation Signal)
CC-LT-2292-1 PCCW Head Tank 19B Level (NNS Header 1153DB4 l
Isolation Signal) 1 CC-LT-2292-2 PCCW Head Tank 19B Level (NNS Header 1153DB4 Isolation Signal) i CC-LT-2292-3 PCCW Head Tank 19B Level (NNS Header 1153DB4 Isolation Signal) l CS-FT-7325 CS-P-2A Chg Pmp Disch Flow (Pump Deadhead 1153HB4 Protection)
CS-FT-7326 CS-P-2B Chg Pmp Disch Flow (Pump Deadhead 1153HB4 Protection)
FW-FT-4214-2 SG A EFW Hdr Flow (Isolation of Flow to 1153DB5 Faulted SG)
M New Hampshiro Yankie March 8, 1990 TABLE 1 SAFETY-RELATED ROSEMOUNT TRANSMITTERS TRANSMITTER FUNCTIONMODEL E,
FW-FT-4214-4 SG A EFW Hdr Flow (Isolation of Flow to 1153DB5 Faulted SG)
FW-FT-4224-2 SG B EFW Hdr Flow (Isolation of Flow to 1153DB5 Faulted SG).
FW-FT-4224-4 SG B EFW Hdr Flow (Isolation of Flow to 1153DB5 Faulted SG)
FW-FT-4234-2' SG C EFW Hdr Flow (Isolation of Flow to 1153DB5 Faulted SG)
FW-FT-4234-4 SG C EFW Hde Flow (Isolation of Flow to 1153DB5 Faulted SG)
FW-FT-4244-2 SG D EFW Hdr Flow (Isolation of Flow to 1153DB5 Faulted SG)
FW-FT-4244-4 SG D EFW Hdr Flow (Isolation of Flow to 1153DB5 Faulted SG)
FW-PT-4252 Condensate Storage Tank Level (FW-P-37A 1153GB5
_ Suction Pressure)
FW-PT-4257 Condensate Storage Tank Level (FW-P-37B 1153GB5 Suction Pressure)
SW-LT-6129 Cooling Tower Loop A SW Basin Level.
1153DB5 SW-LT-6139 Cooling Tower Loop B SW Basin Level 1153DB5 SW-PT-8272 SW-P-41A/C Swp Disch Hdr Press (CT Tower 1153DB6 Actuation Signal)
SW-PT-8273 SW-P-41A/C.Swp Disch Hdr Press (CT Tower
-1153DB6 Actuation-Signal)
SW-PT-8274' SW-P-41A/C Swp Disch Hdr Press (CT Tower 1153DB6 Actuation Signal)
SW-PT-8282 SW-P-41B/D Swp Disch Hdr Press (CT Tower 1153DB6 Actuation-Signal)
SW-PT-8283
_SW-P-41B/D Swp Disch Hdr Press (CT Tower 1153DB6 Actuation Signal)
SW-PT-8284 SW-P-41B/D Swp Disch Hdr Press (CT Tower 1153DB6 Actuation Signal)
RC-PT-455 Pressurizer Pressure 1154GP9 RC-PT-456 Pressurizer Pressure 1154GP9 RC-PT-457 Pressurizer Pressure 1154GP9 RC-PT-458 Pressurizer Pressure 1154GP9 FW-LT-551 Steam Generator A Narrow Range Level 1154DP4
'FW-LT-517 Steam Generator A Narrow Range Level 1154DP4 FW-LT-518 Steam Generator A Narrow Range Level 1154DP4 FW-LT-519 Steam Generator A Narrow Range Level 1154DP4
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w w
3, N w H:mpshire Yank:e March 8. 1990 TABLE 1 SAFETY-RELATED ROSEHOUNT TRANSMITTERS TRANSMITTER FUNCTION MODEL NO, FW-LT-552 Steam Generator B Narrow Range Level 1154DP4 FW.LT-527 Steam Generator B Narrow Range Level 1154DP4 FW-LT-520 Steam Generator B Narrow Range Level 1154DP4 FW-LT-529.
Steam Generator B Narrow Range Level 1154DP4 FW-LT-553 Steam Generator C Narrow Range Level 1154DP4 FW-LT-537 Steam Generator C Narrow Range _ Level 1154DP4 FW-LT-538 Steam Generator C Narrow Range Level 1154DP4 FW-LT-539 Steam Generator C Narrow Range Level 1154DP4
~ Steam Generator D Narrow Range' Level' 1154DP4 FW-LT-554 FW-LT-547 Steam Generator D Narrow Range Level 1154DP4 FW-LT-548 Steam Generator D Narrow Range Level 1154DP4 FW-LT-549 Steam Generator D Narrow Range Level 1154DP4 RC-LT-459 Pressurizer Level 1154DP5 RC-LT-460 Pressurizer Level 1154DP5 RC-LT-461 Pressurizer Level 1154DP5 s,
f
New H:mpshiro Yankso March 8, 1990 9
h to NYN-90056 Proposed Draft Bulletin on Loss of Fill-Oil in Rosemount Transmitters Response to Reportina Reauirements:
Operatina Reactors
)
1 i
1 l
l i
Niw H:mpshira Ycnk33 L,
March 8, 1990-L Pronosed Draft' Bulletin on Loss of F111-011 in Rosemount Transmitters Response to Reportina Recuirements: Operatina Reactors NRC Reoortina Reouirement #1(a)
Confirms that those Requested Actions for Operating Reactors in Items 1, 2, 3, 4, and SLthat are to be completed within 120 days after receipt of this bulletin have-been completed and that programs are in place to perform the remaining
-requested actions..
NHY Response The status or scheduled completion for the Requested Actions for Operating Reactors in Items 1,2,3,4 and 5 of the proposed draft Bulletin is as follows:
Item 1:
This item has been completed.
Item 2:
This' item will be complete by 3/14/90.
Item 3:
The major elements of the program, the establishment of the preventive maintenance actions and the first two monthly channel checks for the majority of the channels is complete. The procedure describing the trending program is drafted and expected j'
to be formally approved by 3/14/90. The procedure documenting the operability acceptance criteria and associated testing expected to be approved by 3/30/90. The review of the calibration information has not identified a need to verify the operability of any of the transmitters on Table 1.
Item 4:
This item has been completed.
Item 5:
A basis for continued operation is not required at this time, therefore this item is not applicable.
NRC Reportina Reauirement #1(b)
,i
ldentifies the indicated manufacturers the model number; the safety-related 4
I system the transmitter was utilized in the approximate amount of time in services the corrective actions taken: and the disposition (e.g., returned to j
vendor for analysis) of transmitters, including those~ identified while performing Item 2 of Requested Actions for Operating Reactors above,.that are believed to I
have exhibited symptoms indicative of-loss of fill-oil or have been confirmed to have experienced a loss of fill-oil.
NHY Response At the present time there are no transmitters that have been confirmed to have a
. fill-oil loss failure at.Seabrook. Ihere is one transmitter which is under study
. because a review cf calibration records indicates that it may be exhibiting the
-early signs of fill-oil loss.
The following information applies to this transmitter:
I l
N:w H:mpshire Ydnk30 e
March 8, 1990 k
Indicated Manufacturer: Rosemount T
.Model Numbers -1153 System:-
Function: Flow measurement for isolation of EPW flow to a faulted Steam Generator..
Time in Service:
Installed since September, 1985.
_ Observed Symptoms:
The transmitter has drifted in the same direction over two calibration periods.
Corrective Action Taken: The transmitter has been identified to be calibrated more frequently to determine if it continues to display the symptoms of fill-oil leakage.
If, the transmitter continues to display the symptoms of fill-oil leakage then the actions described.in Enclosure 1 Response to Action #2 will be implemented.
Disposition:
The transmitter is being evaluated in accordance with the program.
NRC Reportina Reauirement #1(c)
-Identifies the safety-related system in which the Model 1153 or 1154 transmitters from the manufacturing lots that have been identified by Rosemount as having a high failure fraction due to loss of fill-oil are utilit.ed and provides a schedule for replacement of these transmitters which are in use in the reactor protection-or engineered safety features actuation systems.
NHY Response There are no Model 1153 or 1154 transmitters from the manufacturing lots that have been identified by Rosemount as having a high failure fraction-due to loss of fill-oil utilized in the reactor protection or engineered safety-features actuation system.
NRC Reportina Reauirement #2 s
Transmitters that, subsequent to providing the response required by ITEM 1 above, exhibit. symptoms of loss of fill-oil or are confirmed to have experienced a loss of fill-oil should be reviewed for reportability under existing NRC regulations.
If determined not to be reportable, addressees are requested to document and maintain, in.accordance with plant procedures, information consistent with that requested in Item 1 (b) above for each suspect transmitter identified.
NHY Response If a.Rosemount Model 1153 or 1154 transmitter exhibits the symptoms of loss of fill-oil or are confirmed to have experienced a loss of fill-oil this condition will ba reviewed for reportability under existing NRC regulations.
If it is determined not to be reportable, information consistent with that requested in
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. March 8, 1990 NHY Response
- Item Ib'of the Reporting'. Requirements for Operating Reactors of the Draft Bulletin will-be documented and maintained in accordance with plant procedures.-
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