ML20034G380
| ML20034G380 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 03/01/1993 |
| From: | Parker T NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-90-001, IEB-90-1, NUDOCS 9303090426 | |
| Download: ML20034G380 (8) | |
Text
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h Nodhem States Power Company 414 Nicollet MaH Minneapoks, Minnesota 55401 Telephone (612) 330-5500 March 1, 1993 NRC Bulletin 90-01 Supplement 1 a
US Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555 s
MONTICELID NUCLEAR GENERATING PIANT Docket No. 50-263 License No. DPR-22 Response to NRC Bulletin No. 90-01 Supplement 1 Loss of Fill-Oil In Transmitters Manufactured By Rosemount The following information is provided in response to the reporting requirements contained in NRC Bulletin 90-01, Supplement 1, " Loss of Fill-Oil in Transmitters Manufactured by Rcsemount."
Reporting Requirement No. 1 states:
[ Provide within 60 days) a statement whether the licensee will take the actions requested [by NRC Bulletin 90-01, Supplement 1).
Resnonss The actions requested by NRC Bulletin 90-01, Supplement 1, that are applicable to the Rosemount transmitters located at the Monticello Nuclear Generating Plant, have been completed.
Reporting Requit 2ent No. 2 states:
With regard to the action requested above that the licensee is taking
[ provide]:
a.
A list of the specific actio 3 L.a t the licensee will complete to meet Item 1 of L aquested Actions for Operating Reactors provided in [NRC Bulletin 90-01, Supplement 1.]
b.
The schedule for completing licensee action to meet Item 1 of Requested Action provided in [NRC Bulletin 90-01, Supplement 1.]
c.
When completed, a statement confirming that Items 1 and 2 of requested Actions for Operating Recctors provided in [NRC Bulletin 90-01, Supplement 1] have leen completed.
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USNRC NORTHERN STATES POWER COMPANY March 1, 1993 Page 2 m * *.*
Response
a.
Details of specific actions taken are contained in Attachment 2.
b.
Actions to meet Item 1 of the Requested Actions have been completed as applicable, c.
Actions to meet Item 1 and 2 of the Requested Actions have been completed as applicable.
Reporting Requirement No. 3 states:
{ Provide] a statement identifying those actions requested by the NRC that the licensee is not taking and an evaluation which provides the bases for not taking the requested actions.
Response
All applicable actions requested by the NRC have been completed.
See for additional detail.
With this response we are making the following new commitment:
We will control spare Rosemount Model. 1153 Series B transmitters that were mart :ictured prior to July 11, 1989 and have not been refurbished to prevt. their use in safety-related applications of 500 psi or more.
Please contact Merv Engen n: (512) 295-1291 if you have any question related to the infor
- ion we have p vided.
/'
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' Thomas M Parker Director Nuclear Licensing c:
Regional Administrator - III, NRC NRR Project Manager, NRC Sr Resident inspector, NRC State of Minnesota Attn: Kris Sanda J Silberg Attachments:
1)
Affidavit 2)
Monticello Responst to Requested Actions for Operating Reactors l
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9 1
ATTACHMENT 1 UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT LOSS OF FILL-01L IN TRANSMITTERS MANUFACTURED BY ROSEMOUNT his letter is Northern States Power Company, a Minnesota corporation, with t90-01, Supplement submitting information requested by NRC Bulletin This letter contains no restricted or other defense information.
NORTHERN STA S POW C MPANY s
/ W4 By
/Th'omas M Parker Director Nuclear Licensing
/f k 3 before me a notary public in and On this day of h
l for said County, personah y appeared Thomas M Parker, Director Nuc ear h i d to Licensing, and being first duly sworn acknowledged that he is aut or zeCompany execute this document on behalf of Northern States Powerkno d that it is not information, and beli f the statements made in it are true an interposed for delay.
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i ATTACHMENT 1 l
UNITED STATES NUCLEAR REGULATORY COMMISSION j
NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PIANT DOCKET NO. 50-263 LOSS OF FILL-01L IN TRANSMITTERS MANUFACTURED BY ROSEMOUNT i
I Northern States Power Company, a Minnesota corporation, with this letter is submitting information requested by NRC Bulletin 90-01, Supplement 1.
This letter contains no restricted or other defense information.
NORTHERN STA S POV t C MPANY r
By SMd
/Th'omas M Parker-
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Director Nuclear Licensing l
Onthis!
day of O
/f N before me a notary public in and for said County, persona'TIy appeared Thomas M Parker, Director Nuclear Licensing, and being first duly sworn acknowledged that he is authorized to execute this document on behalf of Northern States Power Company, that he knows the contents thereof, and that to the best of his knowledge, information, and belief the statements made in it are true and that it is not interposed for delay.
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ATTACHMENT 2 Monticello Resoonse to Recuested Actions for Ooerating Reactors Recuested Action No. 1 Review plant records and identify any Rosemount Model 1153 Series B, Model 1153 Series D, and Model 1154 transmitters manufactured before July 11, 1989, that are used or may be used in the future in either safety-related systems or systems installed in accordance with 10 CFR 50.62 (the ATUS rule), and a.
Expeditiously replace, or monitor for the life of the transmitter on a monthly basis using an enhanced surveillance monitoring program, any transmitters that have a normal operating pressure greater than 1500 psi and that are installed in reactor protection trip systems, ESF actuation systems or ATWS systems. Action for those transmitters that have not met the Rosemount psi-month threshold criterion should be expedited. At their discretion, licenses may monitor using an enhanced surveillence program at least once every refueling cycle, but not exceeding 24 months, transmitters in this category if the appropriate psi-month threshold critorion recommended by Rosemount has been reached, and the monitoring interval is justified based upon transmitter performance in service and its specific safety function.
The justification should show tnat a sufficiently high level of reliability for the function is provided by the redundancy or diversity of applicable instrumentation and control systems, commensurate with the importance of the function, when considered in conjunction with the overall performance of the reactor protection trip system, ESF actuation systems, or ATWS system.
Provide to the NRC a copy of the licensee justification to extend the enhanced surveillance program beyond the monthly test interval for transmitters that have reached the appropriate psi-month threshold criterion recommended by Rosemount.
b.
Replace, or monitor for the life of the transmitter on a quarterly basis using an enhanced surveillance monitoring program, any transmitters that have a normal operating pressure greater than 1500 psi and that are used in safety-related applications but are not installed in reactor protection trip systems, ESF actuation systems, or ATWS systems. At their discretion, licensees may monitor using an enhanced surveillance program at least once every refueling cycle, but not exceeding 24 months, transmitters in this category if the appropriate psi-month threshold criterion recommended by Rosemount has been reached, and the monitoring interval is justified based upon transmitter performance in service and its specific function.
Provide to the NRC a copy of the licensee justification to extend the enhanced surveillance program beyond the quarterly test interval for transmitters that have reached the appropriate psi-month threshold criterion recommended by Rosemount.
. y 1
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l February 10, 1993 Page 2
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Monticello Response to Recuested Actions for Operatine Reactors i
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c.
[For BWRs] Replace, or monitor on a monthly basis using an' l
enhanced surveillance monitoring program, until the transmitter j
reaches the appropriate psi-month threshold criterion recommended by Rosemount, any transmitters that have a normal operating..
pressure greater than 500 psi and less than or equal to 1500 psi, i
that are installed in reactor protection trip systems, ESF j
actuation systems or ATWS systems. On a case-by-case basis except for transmitters that initiate reactor protection or ATUS trips for high pressure or low water level, licensees may monitor using j
an enhanced surveillance program at least once every refueling j
cycle, but not exceeding 24 months, if sufficient justification is.
provided based upon transmitter performance in service and its specific safety function.
The' justification should show that a sufficiently high level of reliability for the function is provided by the redundancy or diversity of applicable j
instrumentation and control systems, commensurate with the importance of the function, when considered in conjunction with the overall performance of the reactor protection trip system, ESF j
actuation systems, or ATWS system. ~ Provide to the NRC a copy of the licensee justification to extend the enhanced surveillance I
program beyond the monthly test interval.
[For PWRs] Replace, or monitor at least once every refueling 5
cycle, but not exceeding 24 months, using an enhanced surveillance q
program until the transmitter reaches the appropriate psi-month threshold criterion recommended by Rosemount, any transmitters that have a normal operating pressure greater than.500 psi and i
4 less than or equal to 1500 psi and that are installed in reactor i
protection trip systems., ESF actuation systems, or ATWS systems.
d.
Replace, or monitor at least once every refueling cycle, but not exceeding 24 months, using an enhanced surveillance monitoring i
program until the transmitter reaches the appropriate psi-month j
threshold criterion recommended by Rosemount, any transmitters used in safety-related systems that have a normal operating pressure greater than 500 psi and.less than or equal to 1500 psi, l
and that are not installed in reactor protection trip systems, ESF actuation systems, or ATkS systems.
i e.
At licensee discretion, exclude from'the enhanced surveillance program any transmitters that have a normal operating pressure f
greater than 500 psi and less than or equal to 1500 psi that have reached the appropriate psi-month threshold criterion recommended i
by Rosemount (60,000 psi-months or 130,000 psi-months depending on j
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February 10, 1993 i
Page 3 I.
Monticello Response to Recuested Actions for Operatinc Reactors a
the range code of the transmitter). A high degree of confidence should be maintained for detecting failure of these transmitters caused by a loss of fill-oil and a high degree of reliability should be maintained for the function consistent with.its safety significance, f.
At licensee discretion, exclude from the enhanced surveillance program any transmitters that have a normal operating pressure i
less than or equal to 500 psi. A high degree of confidence should
)
be maintained for detecting failure of these transmitters caused i
by a loss of fill-oil and a high degree of reliability should be i
maintained for the function consistent with its safety l
significance, j
I
Response
P a.
This item is not applicable. The Monticello Nuclear Generating Plant has nc Rosemount Model 1154 transmitters installed and has no Model 1153, Series B, or Model 1153, Series D transmitters installed in applications with a normal operating pressure greater than 1500 psi.
b.
This item is not applicable. The Monticello Nuclear Generating l'I Plant has no Rosemount Model 1154 transmitters installed and has no Model 1153 Series B, or Model 1153 Series D transmitters installed in applications with a normal operating pressure greater j
than 1500 psi.
c.
[For BWRs] The Monticello Nuclear Generating Plant has no Rosemount Model 1153 Series B, Model 1153 Series D or Model 1154 transmitters-ins alled in the ATWS system. Rosemount Model 1153 Series B transmitters are installed in the reactor protection trip system and ESF systems and are subject to normal operating pressures greater than 500 psi but less than or equal to 1500 psi.
j These transmitters have either had the sensing modules replaced by l
Rosemount with new modules manufactured after July 11 1989 or have reached the psi-month threshold criterion recommended by Rosemount and thus will be excluded from an enhanced surveillance program.
j i
d.
Rosemount Model 1153 Serias B transmitters are installed in safety related systems that have normal operating pressures greater than 500 psi but less than or equal to 1500 psi.
These transmitters have reached the psi-month threshold criterion recommended by l
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February l 10, 1993 l
Page 4 Monticello Resnonse to Reouested Actions for Operatine Reactors 1
I Rosemount and thus will excluded from an enhanced surveillance j
program.
j e.
Rosemount Model 1153 Series B transmitters are installed in the reactor protection trip system and ESF systems and are subject to' normal operating pressures greater than 500 psi but less than or i
equal to 1500 psi. These transmitters have either had the sensing modules replaced by Rosemount with new modules manufactured after July 11, 1989 or have reached the psi-month threshold criterion recommended by Rosemount and thus will be excluded.from an j
enhanced surveillance program. We recognire the need to detect potential failures due to loss of fill-oil and maintain functional l
reliability.- We feel we have taken appropriate actions.to
-l maintain a high degree of confidence in these transmitters, j
i f.
Rosemount Model 1153 Series B transmitters are installed in safety-related systems and are subject to normal operating j
pressures less than 500 psi.
These transmitters will'not be included in an enhanced surveillance program.. We recognize the
.[
need to detect potential failures due to loss of fill-oil' and maintain functional reliability. We feel we have,taken -
l appropriate actions to maintain a high degree of confidence in-l these transmitters.
Rosemount Model 1153 Series B. transmitters, manufactured prior to July ll, f
1989, are also contained in spare' stock-at the Monticello Nuclear Generating Plant. A number of these transmitters have been refurbished with sensing modules manufactured after July 11, 1989 for use as spares'in the reactor j
protection trip system, ESF systems and safety-related systems with normal l
operating pressures greater then 500 psi Controls have been established to prevent-the use of the remaining spare Rosemount Model 1153 Series B i
transmitters in safety-related applications of 500 psi or more.
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Reouested Action No. 2 I
I Evaluate the enhanced surveillance monitoring program to ensure that the.
program provides measurement data with an accuracy range consistent with
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that needed for comparison with manufacturer drift data criteria for j
determining degradation caused by a loss of fill-oil.
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Attachment.2
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February 10, 1993 j
Page 5
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Monticello Response to Recuested Actions for Operatine Reactors i
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Response
i An enhanced surveillance program is no longer required for the Rosemount Model l
1153 Series B transmitters installed at the Monticello Nuclear Generating i
Plant.
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