ML20034G612
| ML20034G612 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 03/05/1993 |
| From: | Cottle W ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GNRO-93-00029, GNRO-93-29, IEB-90-001, IEB-90-1, NUDOCS 9303100230 | |
| Download: ML20034G612 (43) | |
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l RM Gtm MS 33 GO h 601437 6aOS -
March 5, 1993
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U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington, D.C.
20555 Attention:
Document Control Desk
Subject:
Grand Gulf Nuclear Station j
Unit 1 i
-Docket No. 50-416 License No. NPF-29 l
Response to NRC Bulletin 90-01, Supplement 1 i
GNRO-93/00029 Gentlemen:
1 This submittal provides the Grand Gulf Nuclear Station (GGNS) response to NRC Bulletin (NRCB) 90-01, Supplement 1, " Loss of F111-011 in Transmitters Manufactured by Rosemount". Supplement 1 to NRCB 90-01 was issued.to inform licensees of activities taken by the NRC Staff and the nuclear l
l industry in evaluating Rosemount transmitters and to request licensees to
]
take actions to resolve this issue.
The specific safety concern is the j
ability to readily detect failure resulting from a gradual loss of fill-oil i
in Rosemount Model 1153 (Series B and D) and Model 1154 transmitters j
manufactured prior to July 11, 1989.
l i
Our response to the original bulletin (NRCB 90-01) was submitted by letter dated July 19, 1990 (AECM-90/0128) and augmented with additional I
information by letters dated September 12, 1990 and May 16, 1991, respectively. We understand that our response to Supplement 1 supersedes j
the actions requested by the original bulletin.
As committed in our response to the original bulletin, GGNS has established an enhanced surveillance monitoring program'to identify degradation of transmitter function'due to fill-oil loss in Rosemount Model 1153 Series B j
and D transmitters installed in either safety-related systems or systems installed in accordance with 10CFR50.62 (the ATWS rule). This program will remain in effect, with the transmitters listed in Tables. 2, 3, and 4 being monitored on an 18-month (cycle) basis until replacement or the appropriate j
psi-month threshold recommended by Rosemount is achieved. The transmitters listed in Table 1 will be replaced during the next refueling outage, currently scheduled for October 1993.
Transmitters confirmed of having a j
loss of. fill-oil failure will be dispositioned in accordance with our f
non-conformance process or the applicable technical specification.
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March 5, 1993 GNRO-93/00029 Page 2 of 4 Non-installed Rosemount Model 1153 Series B and D transmitters manufactured prior.lo July 11, 1989 will be tagged to preclude inadvertent installation 1
in their current configuration. A review of plant records revealed that no Rosemount Model 1154 transmitters are currently installed at GGNS.
Applications utilizing Rosemount transmitters at GGNS were reviewed against the criteria stipulated by NRCB 90-01, Supplement 1.
Results from this review, including specific actions to be performed and completion schedules e
are discussed in Attachment 1.
GGNS will take the requested actions specified in this supplement. The addendum to Table 1 provides a discussion of the safety function, redundancy, and diversity of the j
transmitters listed in Table 1.
1he addenda to Tables 2 and 3 provide justifications for extending the monitoring frequency for the transmitters listed in Tables 2 and 3 to an 18-month basis.
Supporting reference documents are listed on Attachment 3.
The transmitters listed in Table 4 will be monitored on an 18-month (cycle) basis as recommended by the supplement.
With the enhanced surveillance monitoring program in place and increased awareness by plant personnel of the susceptibility for oil-loss from the transmitters in question, we are confident that symptoms of transmitter fill-oil loss will be detected should they develop.
This information is being submitted under affirmation in accordance with 10CFR50.54(f). As requested by Item 2(c) of the reporting requirements, we will provide written confirmation upon completion of the requested actions of the supplement.
Please contact R. W. Byrd at 601-437-6550 should you have any questions or require additional information regarding this matter.
Yours trul
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a tachments: 1) GGNS Response to NRCB 90-01, Supplement 1
- 2) Oath and Af firmation per 10CFR50.54(f)
- 3) References I
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G9303011/SNLICFLR - 2
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j March 5, 1993 j
GNRO-93/00029 i
J Page 3 of 4 l
i cc:
Mr. R.11. Bernhard (w/a)
Mr. D. C. Ilintz (w/a)
Mr. R. B. McGehee (w/a) j Mr. N. S. Reynolds (w/a) s Mr. II.
I,. Thomas (w/a)
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Mr. Stewart D. Ebneter (w/a)
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Regional Administrator U.S. Nuclear Regulatory Commission
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Region II 101 Marietta St., N.W., Suite 2900 j
Atlanta, Georgia 30323 4
i Mr. P. W. O'Connor, Project Manager (w/2)
Office of Nuclear Reactor Regulation j,
U.S. Nucient Regulatory Commission Mail Stop 13113 1
Washington, D.C.
20555 1
Mr. Alex Marion (w/a) i i
Nuclear Management and Resources Council
[
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1776 Eye St.,
N.W.,
Suite 300 f
j Washington, D.C.
20006-2996 I
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GGNS. Response to NRC Bulle't'in'90-01 I
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G9303011/SNLICFLR - 5 l
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j Grand Gulf Nuclear Station Response to NRC Bulletin 90-01, Supplement 1 Reporting Requiremt,ts Applicable to Operating Reactors 4
i 3
i NRCB Item 1:
Licensees are requested to provide a statement of whether they wi)) take the recommended actions in this j
supplement under " Requested Actions".
L 3
GGNS Response:
GGNS will implement the requested actions recommended
[
in the supplement.
i j
NRCB Ttems 2(a):
Licensees are requested to provide a listing of and 2(b) specific act. ions that will be completed to achieve 4
compliance with Item 1 of the requested actions. This J
listing should include appropriate justification for 4
deviations from actions recommended by the supplement, and a completion schedule for these actions.
GGNS Response:
A point by point comparison between a summarized extract from the requested actions of NRCB 90-01, Supplement I and the corresponding GGNS response j
t follows:
i
]
Requested Actions Licensees are requested to review plant records and i
Item I identify Rosemount Model 1153 Series B, Model 1153 1
Series D, and Model 1154 transmitters manufactured f
before July 11, 1989, that are used or may be used in I
the future in either safety-related systems or systems j
installed in accordance with 10CFR50.62 (the ATWS J
rule), and perform the following requested actions:
I Requested Actions Item 1(a)_
Expeditiously replace, or monitor for the life of the transmitter on a monthly basis using an enhanced surveillance monitoring program, any transmitter that has a normal operating pressure greater than 1500 psi and that are installed in the reactor protection trip system, ESF actuation systems or ATWS systems...
GGNS Res.ponse to item 1(a)
CGNS has no transmitters installed that are enveloped by this category. Rosemount transmitters manufactured prior to July 11, 1989 will be tagged to preclude inadvertent installation in their current configura tion. This action is planned to be completed by March 31, 1993. Model 1154 transmitters manufactured by Rosemount are not used in any plant applications.
G9303011/SNLICFLR - 6
i l
Grand Gulf Nuclear Station Response to NRC Bulletin 90-01, Supplement 1 l
(Continued) 1 Requested Actions Item 1 (Continued) Requested Actions Item 1(b)
I 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...
GGNS Response to Item 1(b}
GGNS has no transmitters installed that are enveloped by this category.
Rosemount transmitters manufactured j
prior to July 11, 1989 will be tagged to preclude inadvertent installation in their current configuration. This action is planned to be completed by March 31, 1993. Model 1154 transmitters I
manufactured by Rosemount are not used in any plant applications.
Requested Actions Item 1(cl Replace, or monitor on a monthly basis using an l
enhanced surveillance monitoring program, until the l
transmitter reaches the appropriate psi-month threshold criterion recommended by Rosemount, any transmitters l
that have a normal operating pressure greater than 500 l
psi and less than or equal to 1500 psi, that are l
installed in reactor protection trip systems, ESF actuation systems, or ATWS systems. On a case-by-case basis except for transmitters that initiate reactor protection or ATWS trips for high pressure or low water level, licensees may monitor esing an_ enhanced surveillance program at least once every refueling cycle, but not exceeding 24 months, if sufficient justification is provided based upon transmitter performance in service and its specific safety function.
GGNS Res_ponse to Item 1(c)
GGNS has 10 transmitters installed that are enveloped by this category.
I l
G9303011/SNLICFLR - 7 l
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Grand Gulf Nuclear Station
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Response to NRC Bulletin 90-01, Supplement 1 (Continued)
\\
Requested Actions GGNS Response to item 1(c) (continued)
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ltem 1 (Continued)
The 5 transmitters listed in Table 1 have accumulated j
53,450 psi-months against the Rosemount threshold j
criteria of 130,000 psi-months. Although the 4
recommended psi-month threshold has not been achieved, i
these transmitters have exhibited stable operation over t
j three calibration cycles. None of these transmitters
{
are used to initiate reactor protection or ATWS trip l
functions. The transmitters listed in Table I will bc l
replaced during the next refueling outage (October 1993). Additional data regarding these transmitters is j
delineated in Table 1 and the attached calibration data i
]
sheets and graphs.
Additional information regarding the safety function, system redundancy and diversity of l
these transmitters is discussed in the addendum to i
Table 1.
4 The remaining 5 transmitters will reach the appropriate
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i psi-month criteria recommended by Rosemount during this l
year (1993). Although the recommended psi-month threshold has not been achieved, these transmitters have exhibited stable operation over three calibration l
I cycles. These transmitters do not initiate reactor
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j protection or ATWS trip functions. As permitted by the bulletin supplement, the monitoring frequency will be
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changed to an 18-month enhanced surveillance program beginning March 31, 1993, until the appropriate psi-month criteria recommended by Rosemount is achieved. Additional data regarding these transmitters along with justification for extending the monitoring i
frequency to an 18-month basis is provided in Tables 2 l
and 3.
t Requested Actions Item 1(d]
1 Replace, or monitor at least once every refueling cycle, but not exceeding 24 months, using an enhanced surveillance monitoring program until the transmitter reaches the appropriate psi-month threshold criterion 2
recommended by Rosemount, any-transmitter used in safety-related systems that have a normal operating l
pressure greater than 500 psi and less than or equal to 1500 psi, and that are not installed in reactor I
protection trip systems, ESF actuation systems, or ATWS systems.
1 G9303011/SNLICFLR - 8
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f Grand Gulf Nuclear Stc?
Response to NRC Bulletin 90-01, Supplement 1 (Continued)
Requested Actions Item 1 (Continued) GGNS Response to item 1(d).
GGNS has 4 transmitters that are enveloped by this category. As recommended by the bulletin supplement, these transmitters will be included in the enhanced monitoring program on an 18-month frequency beginning March 31, 1993 until the appropriate psi-month criteria recommended by Rosemount is achieved. Table 4 provides a listing, along with additional details for these units.
Requested Actions Item 1(c) l At licensee discretion, exclude from the enhanced surveillance program any transmitters that have a normal operating pressure greater than 500 psi and less than or equal to 1500 psi that have reached the appropriate psi-month threshold recommended by' Rosemount (60,000 psi-months or 130,000 psi-months depending on the range code of the transmitter)...
l GGNS Response to Item 1(e) l GGNS has 7 transmitters that are enveloped by this category. As permitted by the supplement, these transmitters will be excluded from the enhanced surveillance program beginning March 31, 1993. A high degree of confidence remains that a loss of fill-oil failure is detectable during the normal 18-month calibration and during channel checks where applicable.
Requested Actions Item 1(f)
At licensee discretion, exclude from the enhanced surveillance program any transmitters that have a normal operating pressure less than or equal to 500 psi...
GGNS Response to Item 1(f)
GGNS has 95 transmitters that are enveloped by this category. As permitted by the supplement, these transmitters will be excluded from the enhanced surveillance program beginning March 31, 1993. A high degree of confidence remains that a loss of fill-oil failure is detectable during the normal 18-month calibration.
G9303011/SNLICFLR - 9
l 1
Grand Gulf Nuclear Station Response to NRC Bulletin 90-01, Supplement 1 (Continued) j 1
l Requested Actions Licensees are requested to evaluate the enhanced Item 2 surveillance program to ensure that the program l
provides measurement data with an accuracy range l
consistent with that needed for comparison with manufacturers drift data criteria for determining degradation caused by a loss of fill-oil.
GGNS Response to item 2 I
l The enhanced surveillance monitoring program has been i
evaluated for measurement data accuracy. The calibration data trending has suf ficient accuracy to detect drift consistent with manufacturers criteria.
The process data trending (monthly) will not be used to satisfy requirements pursuant to this supplement.
t I
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NRCB Item 2(c):
When completed, provide the Staff a statement l
confirming completion of Requested Actions Items 1 and 2 to NRCB 90-01, Supplement 1.
GGNS Response:
We will change the monitoring frequency for the transmitters listed in Tables 2 thru 4 to an 18-month
(
basis until the appropriate psi-month threshold is achieved. This change will be in effect no later than March 31, 1993. The transmitters listed in Table 1 are scheduled to be replaced during the next refueling outage (October 1993). We will provide the Staff with confirmation documenting the status of the above l
actions following replacement of the transmitters I
listed in Table 1.
l NRCB Item 3:
Licensees are requested to identify those requested actions by the NRC that are not being taken along with
}
an evaluation for deviating from the requested actions.
GGNS Response:
GGNS is complying with the requested actions of this supplement.
As permitted by the supplement, the 5 transmitters listed in Tables 2 and 3 will be monitored on an 18-month (refueling cycle) frequency rather than the monthly frequency recommended by the supplement.
Justification for extending the monitoring interval from the supplements recommended monthly monitoring to an 18-month frequency is delineated in the addenda to Tables 2 and 3.
G9303011/SNLICFLR - 10 l
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1 Table 1 i
Reference NRCB Supplement 1 Requested Actions Item 1(c)
Transmitter Transmitter Serial Model ESF/RPS/A1VS Accumulated PSI-month Monitoring j
Number Number Number Application PSI-Months Threshold Function 1E31N086C 418312 1153DB7 ESF 53,450 130,000 Main Steam Line A Flow C PCIS 1E31N089A 418367 1153DB7 ESF 53,450 130,000 Main Steam Line D Flow A PCIS 1E31N089B 418195 1153DB7 ESF 53,450 130,000 Main Steam Line D Flow B PCIS 1E31N089C 418197 1153DB7 ESF 53,450 130,000 Main Steam Line D Flow C FCIS 9
IE31N089D 418198 1153DB7 ESF 53,450 130,000 Main Steam Line D Flow D PCIS I_
1 G9303011/SNLICFLR - 11
1 i
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Table 1 Addendum i
j ADDITIONAL INFORMATION i
Function:
These transmitters provide signals for the main steam line - high flow trip: main steam line high flow could indicate a break in a main steam line. Automatic closure of various valves prevents excessive loss of reactor coolant and release of significant amounts of radioactive material from the reactor coolant pressure boundary. On detection of j
main steam line high flow, the following pipelines are isolated:
i i
a.
All four main steam lines j
b.
Main steam line drain l
liigh flow in each main steam line is sensed by four differential pressure transmitters that sense the pressure difference across the j
flow element in that line.
j System Logic and Sequencing:
When a significant increase in main steam line flow is detected, trip signals are transmitted to the Containment and Reactor Vessel Isolation l
Control System (CRVICS). The CRVICS initiates closure of all main j
steam isolation and drain valves.
I Four instrumentation trip logics are provided to assure protective action when required and to prevent inadvertent isolation resulting l
from instrumentation malfunctions. The trip signal for each i
instrumentation channel initiates a trip logic trip.
The trip signals of the logic divisions are combined in one-out-of-two twice and i
two-out-of-two logic. Divisions 1 or 3 and Divisions 2 or 4 are l
required to initiate main steam line isolation.
Divisions 2 and 3 or Divisions 1 and 4 are required to initiate main steam line drain isolation.
Thus, failure of any one division does not result in inadvertent action.
i System Redundancy and Diversity:
j Redundancy of trip initiation signals for high flow is provided by four differential pressure transmitters connected to each main steam line.
j Each of the four differential pressure transmitters on a given steam i
line is associated with one of four logic divisions and is powered from an independent Class 1E uninterruptible power supply division -
Divisions 1, 2, 3, and 4.
Diversity of trip initiation for main steam line break is provided by main steam line tunnel high space temperature, high differential temperature, main steam line high flow, and low-pressure instrumentation. An increase in space temperature, differential temperature, main steam line flow, or a decrease in pressure will J
initiate main steam line and main steam line drain isolation.
i G9303011/SNLICFLR - 12 i
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i Table 1 Addendum (Continued)
ADDITIONAL INFORMATION Transmitter Performance:
f The transmitters listed in Table 1 were installed in November 1987.
i They have been through three calibration cycles. The trend of cumulative zero drift for all five transmitters has been relatively flat. The trend of cumulative span drift has shown more variability.
Ilowever, it is not directed and does not indicate loss of fill fluid.
i Transmitter calibration data and a graph of cumulative zero and span 1
drift are attached, a
Based on safety function, trip diversity and redundancy, we are confident that the transmitters listed in Table 1 will continue to q
perform their intended function, until replacement during the upcoming i
refueling outage (October 1993).
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Table 2 Reference NRCB Supplement 1 j
Requested Actions Item 1(c)
Transmitter Transmitter Serial Model ESF/RPS/ATWS Accumulated PSI-month Monitoring Number Number Number Application PSI-Months Threshold Function j
1B21N081A 418193 1153DB5 ESF 53,320 60,000 Reactor Vessel r
Level 4
IB21N081C 418194 1153DB5 ESF 53,320 60,000 Reactor I
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1 G9303011/SNLICFLR - 15 i
i Y
Table 2 Addendum JUSTIFICATION FOR EXTENDING ENHANCED SURVEILLANCE MONITORING i
PERIOD TO 18 MONTHS FOR THE TRANSMITTERS LISTED IN TABLE 2 Function:
These transmitters monitor Reactor Pressure Vessel (RPV) water level channels and provides actuation signals to the following systems:
Primary Containment Isolation (Groups 6A, 7, 8, 10)
Main Steam Line Isolation Secondary Containment Isolation Reactor Water Clean Up Standby Gas Treatment Control Room Emergency Filtration Secondary Containment Ventilation Isolation Dampers System Logic and Sequencing 1 Main Steam Isolation Valves One-out-of-Two taken Twice (Divisions 1 or 3 and Divisions 2 or 4) i All other systems 1
Two-Dut-Two (Divisions 2 and 3 or Divisions 1 and 4)
System Diversity:
For pipe breaks inside the containment, diversity is provided by drywell pressure channels. A breach in the Main Steam Line is detectable by main steam line space high temperature and differential high temperature, main steam line high flow and low pressure instrumentation.
1 Transmitter Performance:
The transmitters listed in Table 2 were installed in December of 1987.
l They have been through three calibration cycles.
In the first
{
calibration cycle, a small positive zero drif t of approximately one pntcent of calibrated span was observed. This is compared to a i
positive limit of 3.9% of calibrated span.
During the next two i
calibration cycles, the transmitters have exhibited virtually no drif t.
l Transmitter calibration data and a graph of cumulative zero and span drift is attached. Oil loss lifetime is' calculated by dividing the appropriate zero drif t limit by_the average zero drift rate.
The calculated oil loss lifetime is 17.7 years for 1B21N081A and 14.6 years for IB21N081C.
1 G9303011/SNLICFLR - 16
-i l
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Table 2 Addendum (Continued)
JUSTIFICATION FOR EXTENDING ENHANCED SURVEILLANCE MONITORING PERIOD TO 18 MONTHS FOR THE TRANSMITTERS LISTED IN TABLE 2 Justification:
1 As stated in Reference 1, the analytical model developed by Rosemount for analyzing the loss-of-fill-fluid phenomenon has proven to be quite accurate.
Based on this model, for transmitters with a sustained flat trend, the interval to identify oil loss increases with time in service. For the transmitters listed in Table 2, calibration data trending on an 18-month basis is effective because the calibration interval is small enough relative to the calculated oil loss lifetime to assure detection of oil loss prior to failure.
==
Conclusion:==
Monitoring on a monthly basis would not result in an improvement in j
reliability for the transmitters listed in Table 2.
Calibration data trending is the most effective means for detecting oil loss prior to failure. Although the recommended psi-month threshold has not been achieved, transmitter past performance, application, and redundant safety function, monitoring the transmitters listed in Table 2 on an 18-month (cycle frequency) is adequate for detecting symptoms of fill-oil loss.
I G9303011/SNLICFLR - 17
s I
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G9303011/SNLICFLR - 18
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Page 1
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Page 1
e Table 3 Reference NRCB Supplement 1 Requested Actions Item 1(c)
Transmitter Transmitter Serial Model ESF/RPS/ATWS Accumulated PSI-month Monitoring Number Number Number Application _
PSI-Months _
Threshold Function IE32N061A 418200 1153GB6 ESP 53,320 60,000 Main Steam Line A 1E32N061E 418199 1153GB6 ESF 53,320 60,000 Main Steam Line B IE32N061N 418201 1153GB6 ESF 53,320 60,000 Main Steam Line D G9303011/SNLICFLR - 19
4 8
l Table 3 Addendum a
i JUSTIFICATION FOR EXTENDING ENHANCED SURVEILLANCE MONITORING i
PERIOD TO 18 MONTHS FOR THE TRANSMITTERS LISTED IN TABLE 3 i
Function:
The Main Steam Isolation Valve-Leakage Control System (MSIV-LCS) is designed to minimize the release of fission products which could leak
/
s through the closed MSIVs and bypass the standby gas treatment system after a postulated LOCA. The system is manually initiated after a LOCA. The transmitters listed in Table 3 provide a permissive signal to allow manual initiation only after main steam line pressure has dropped below the set point.
Redundancy and Diversity:
The MSIV-LCS consists of two subsystems: inboard and outboard. Each subsystem has instrumentation, controls and power sources which are separate and independent from each other. Either system may be manually initiated af ter a LOCA. This system is not required in itself to be diverse; it is interlocked by diverse parameter inputs.
Tr_ansmitter Performance:
~
The transmitters listed in Table 3 were installed in December of 1987.
They have been through three calibration cycles.
In the first calibration cycle a small positive zero drift of approximately one
[
percent of calibrated span was observed. As can be seen from the attached calibration data and graphs, the trend for all three 1
transmitters is quite flat. Oil loss lifetime is calculated by dividing the appropriate zero drift limit by the average zero drift rate.
The calculated oil loss lifetimes are:
1E32N061A 40.5 years 1E32N061E 97.0 years i
1E32N061N 19.5 years Justification:
}
i i
As stated in Reference 1, the analytical model developed by Rosemount for analyzing the loss-of-fill-fluid phenomenon has proven to be quite accurate.
Based on this model, for transmitters with a sustained flat trend, the interval to identify oil loss increases with time in service.
For the transmitters listed in Table 3, calibration data trending on an 18-month basis is effective, because the calibration interval is small enough relative to the calculated oil loss lifetime to assure that oil loss is detected prior to failure.
G9303011/SNLICFLR - 20 i
1
Table 3 Addendum (Continued)
JUSTIFICATION FOR EXTENDING ENHANCED SURVEILLANCE MONITORING PERIOD TO 18 MONTHS FOR TEE TRANSMITTERS LISTED IN TABLE 3 i
==
Conclusion:==
1 Monitoring on a monthly basis would not result in an improvement in reliability for the transmitters listed in Table 3.
Calibration data trending is the most effective means for detecting oil loss prior to failure. Although the recommended psi-month threshold has not been l
j achieved, transmitter past performance, application, and redundant j
safety function, monitoring the transmitters listed in Table 3 on an 18-month (cycle frequency) is adequate for detecting symptoms of fill-oil loss.
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Table 4 Reference NRCP Supplement 1 Requested Actions Item 1(c)
Transmitter Transmitter Serial Model ESF/RPS/ATWS Accumulated PSI-month Monitoring Number Number Number Application fS'-Months Threshold Function IB21N027A 418478 1153DD5 No 52,300 60,000 Reactor Vessel Shutdown Level A 1B21N027B 418479 1153DD5 No 52,300 60,000 Reactor Vessel Shutdown Level B IB21N644C 418477 1153DD5 No 6,640 60,000 Reactor Vessel Fuei Zone Level 1B21N044D 418476 1153DD5 No 59,L60 60,000 Reactor Vessel Fuel Zone Level 1
i t
(
l G9303011/SNLICFLR - 23
i_
i e
Attachmant 2 Oath and Affirmation for NRC Bulletin 90-01, Supplement 1 per 10CFR50.54(f)
G9303011/SNLICFLR - 24
t L
e i
References 1)
Rosemount Report D9200129, Status Report on Oil Loss Rosemount Model j
1153 Series B/D and 1154 Transmitters 2)
Rosemount Technical Bulletin #4, Dated 12/22/89 l
i I
I l
1 i
i l
i I
G9303011/SNLICFLR - 26
s.
BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION LICENSE NO. NPF-29 DOCKET NO. 50-416 IN THE MATTER OF MISSISSIPPI POWER 6 LIGHT COMPANY and SISTEM ENERGY RESOURCES, INC.
and SOUTH HISSISSIPPI ELECTRIC POWER ASSOCIATION and ENTERGY OPERATIONS, INC.
AFFIRMATION I, M. J. Meisner, state that I am Director, Nuclear Safety & Regulatory Affairs (GGNS) of Entergy Operations, Inc.; that on behalf of Entergy Operations, Inc., System Energy Resources, Inc., and South Mississippi Electric Power Association I am authorized by Entergy Operations, Inc. to sign and file with the Nuclear Regulatory Commission, this response to NRC Bulletin 90-01, Supplement I for the Grand Gulf Nuclear Station; that I signed this application as Director, Nuclear Safety & Regulatory Affairs (GGNS) of Entergy Operations, Inc.; a id that the statements made and the matters set forth therein are true a d correct to the best of my knowledge, information and belief.
i f
Y
- .[
M. J. Meisner l
l STATE OF MISSISSIPPI l
COUNTY OF CLAIBORNE SUBSCRIBED AND SWORN TO before me a Notary Public, in and for the County and State above named, this 8 b day of 27h1
, 1993.
(SLAL) 1 51 n,n My commission expires:
anAm24.mf G9303011/SNLICFLR - 25 f
'