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| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC | | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC | ||
| page count = 22 | | page count = 22 | ||
| project = TAC:53114 | |||
| stage = Other | |||
}} | }} | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:QVg | ||
QVg | 'A@ | ||
Telephone (412) 393-6000 Nuclear Group | Telephone (412) 393-6000 Nuclear Group | ||
[$,,87,p*,,,,p4,3377. coa 4 | [$,,87,p*,,,,p4,3377. coa 4 June 17, 1985 Division of Licensing U.S. Nuclear Regulatory Commission Attn: Steven A. Varga, Chief Operating Reactors Branch No.1 Division of Licensing Washington, DC 20555 | ||
==Reference:== | ==Reference:== | ||
Beaver Valley Power Station Unit No. 1 Docket No. 50-334, License No. DPR-65 Preliminary Safety Evaluation on Generic Letter 83-28, Itun 4.2.1 Gentlemen: | Beaver Valley Power Station Unit No. 1 Docket No. 50-334, License No. DPR-65 Preliminary Safety Evaluation on Generic Letter 83-28, Itun 4.2.1 Gentlemen: | ||
By letter dated April 24, 1985, the NRC provided a Preliminary Safety Evaluation (SE) on Generic Letter 83-28, Items 4.2.1 and 4.2.2, based on our November 4, 1983 and October 30, 1984 submi ttals. | By {{letter dated|date=April 24, 1985|text=letter dated April 24, 1985}}, the NRC provided a Preliminary Safety Evaluation (SE) on Generic Letter 83-28, Items 4.2.1 and 4.2.2, based on our November 4, 1983 and October 30, 1984 submi ttals. | ||
The Preliminary SE concluded that our position on Item 4.2.2 is acceptable, however, our position on Item 4.2.1 requires additional justification for the 18-month preventive maintenance frequency on the reactor trip breakers. | The Preliminary SE concluded that our position on Item 4.2.2 is acceptable, however, our position on Item 4.2.1 requires additional justification for the 18-month preventive maintenance frequency on the reactor trip breakers. | ||
As stated in our October 30,1984 submittal, we based the 18-month frequency on acceptable perfonnance and results from prior preventive maintenance, surveillance testing, and reactor trips. To elaborate on this, the attached tables and figures sumuarize the history of the reactor trip breakers. | As stated in our October 30,1984 submittal, we based the 18-month frequency on acceptable perfonnance and results from prior preventive maintenance, surveillance testing, and reactor trips. | ||
To elaborate on this, the attached tables and figures sumuarize the history of the reactor trip breakers. | |||
Table 1 summarizes the repairs perfonned on each breaker. As indicated in the table, most of the repairs involved either the circuit or main contacts. Only one repair required maintenance on the UVTA and in this case it was because the UVTA would not allow the breaker to stay closed. | Table 1 summarizes the repairs perfonned on each breaker. As indicated in the table, most of the repairs involved either the circuit or main contacts. Only one repair required maintenance on the UVTA and in this case it was because the UVTA would not allow the breaker to stay closed. | ||
Table 2 provides an estimate of past cycle history for the period 1975 thru June 1, 1983. | Table 2 provides an estimate of past cycle history for the period 1975 thru June 1, 1983. | ||
p p | p p | ||
t pg#WMr e | ,' t pg#WMr e | ||
I Braver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 Preliminary Safety Evaluation on Generic Letter 83-28, Item 4.2.1 | I Braver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 Preliminary Safety Evaluation on Generic Letter 83-28, Item 4.2.1 Page l Tables 3 and 4 provide estimates of expected breaker cycles using the testing criteria that resulted from the Salem ATWS event. | ||
Page l Tables 3 and 4 provide estimates of expected breaker cycles using the testing criteria that resulted from the Salem ATWS event. Table 3 uses l | Table 3 uses l | ||
while Table 4 is based on 10 reactor trips per year. In both estimates, | the test and trip data that occurred in the period 1975 thru June 1,1983; while Table 4 is based on 10 reactor trips per year. | ||
200 breaker cycles are not exceeded in an average 18-month period | In both estimates, 200 breaker cycles are not exceeded in an average 18-month period. | ||
Figure 1 shows the number of reactor trips per year and indicates a decrease to below 10 trips per year. | Figure 1 shows the number of reactor trips per year and indicates a decrease to below 10 trips per year. | ||
Figures 2 thru 16 summarize the trended parameters with data dating | Figures 2 thru 16 summarize the trended parameters with data dating i | ||
I In summary, we believe that the infonnation provided in this submittal justifies our position regarding the frequency for preventive maintenance on reactor trip breakers, | back to 1976 for some parameters. | ||
J. . Carey | I In summary, we believe that the infonnation provided in this submittal justifies our position regarding the frequency for preventive maintenance on reactor trip breakers, t | ||
Figures 1 thru 16 | If you have any questions regarding this infonnation, please contact my office. | ||
Beaver Valley Power Station Shippingport, PA | l Very tru y yours, J. | ||
c/o Document Management Branch | . Carey l | ||
Washington, DC | Vice President i | ||
Direc. tor, Safety Evalaution & Control Virginia Electric & Power Company | Nuclear Group Attachments: Tables 1 thru 4 f | ||
One James River Plaza Richmond, VA | Figures 1 thru 16 cc: Mr. W. M. Troskoski, Resident Inspector U.S. Nuclear Regulatory Connission Beaver Valley Power Station Shippingport, PA 15077 U.S. Nuclear Regulatory Canmission | ||
[ | |||
c/o Document Management Branch Washington, DC 10555 l | |||
I | Direc. tor, Safety Evalaution & Control Virginia Electric & Power Company l | ||
P.O. Box 26666 One James River Plaza Richmond, VA 23261 l | |||
I t | |||
N i | |||
e I | |||
TABLE 8 Reactor Trio /Byoass Repairs e | TABLE 8 Reactor Trio /Byoass Repairs e | ||
MWR grea ke r | MWR grea ke r Cate Feesir Reason Detection CTA 1/7/82 Replaced Main Contacts Main Contacts out Preventive 826451 of limits. | ||
CTA | Maintenance 8/22/83 Check out ok Breaker would not Time Response 837717 and cycled, close. | ||
11/06/84 | Test. | ||
l | 11/06/84 Replaced Aut. Switch Aux. Switch Contacts Preventive 848322 Assembly. | ||
Burnt & Pitted Maintenance 12/24/84 Adjusted UVTA Breaker would not Su rve i l la nce 843056 Stay closed 843136 RTS 1/13/82 Replaced Main contacts Loose Contact Surfaces Preventive 826454 Maintenance CvA 3/6/82 Adjusted Main Contacts M$in Contacts out of Preventive 826464 Limits Maintenance 8/10/32 Replaced fuse and adjusted Blowing control power Surve i l la nce 822039 lever on X relay Fuse 822893 BY3 5/23/80 Replaced closing coil Breaker would not Surveillance 800687 stay closed 1/15/82 Replaced Phase 8 Main Contacts out Preventive 826455 Main contacts. Mjusted cf Limits. | |||
Maintenance Phase A h C | |||
] | |||
i 6/4/82 Cleaned Closing Coit Breaker would not Surveillance 821161 Stay Closed 11/26/32 Replaced fuse and Blowing Control Powe r Surveillance 822893 adjusted lever on fuse 822039 X relay 9/13/83 Replaced Control Relay Control Relay housing Su rve i l la nce 831688 i | |||
b roken 10/12/83 No problem found Breaker would not Surveillance 832074 close I | |||
i 10/17/83 Replaced Control Relay Relay Broken 837573 j | |||
I l | |||
._,_,s_. | |||
TABLE 2 RecctOr Trip Creaker Cyclo CICtery a s o f J urie 1. 1983 CST 1.1.7 | TABLE 2 RecctOr Trip Creaker Cyclo CICtery a s o f J urie 1. | ||
Se rvice | 1983 CST 1.1.7 MSP 1.14 MSP 1.04,5 PMP Sma ke r Ester Cycles Total mer Cycles Total Rumber Cycles Total Nuebe r Cycles Total Trips Dsts /fest Cvetes Tests | ||
/ Test Cvele_1 Tests | |||
/ Test Cveles Tests | |||
/ Test Cveles RIA 96 2 | |||
192 5 | |||
4 20 40 1 | |||
40 6 | |||
7 42 126 RTS 2 | |||
192 4 | |||
4 16 41 1 | |||
41 6 | |||
7 42 126 B~r A 96 1 | |||
96 N/A 40 1 | |||
40 6 | |||
7 42 0 | |||
frv3 96 1 | |||
96 N/A 41 1 | |||
41 5 | |||
7 36 0 | |||
Ave rage Ave rage Ave rage Breake r Total Yea rs Cycles Cycles / | |||
Cycles / | |||
Se rvice | |||
/ Year Months 18 Months RTA 420 7 | |||
60.00 5.00 90.00 RTS 417 7 | |||
59.57 4.96 89.36 BYA 178 7 | |||
25.43 2.12 38.14 BYB 172 7 | |||
2f.57 2.05 36.86 4 | |||
l l | l l | ||
I l | l I | ||
l | |||
r TASLE 3 Reacter Trip Creaker Cyclo Ettimate U,i ne Pa s t Test History i | r TASLE 3 Reacter Trip Creaker Cyclo Ettimate U,i ne Pa s t Test History i | ||
Se rvice | CST 1.T.7 MSP 1.14 MSP 1.04.5 PHP l | ||
Bresher taber Cycles Tctal numbe r Cycles Total Numbe r Cycles Total alumbe r Cycles Total Trips Tests / Test CWies Tests | |||
/ Test Cycles Tests | |||
/ Test Cveles Tests | |||
/ Test Cycles RfA 96 3 | |||
258 8 | |||
40 40 3 | |||
120 6 | |||
26 156 126 l | |||
RTS 96 3 | |||
253 4 | |||
8 32 41 3 | |||
123 6 | |||
26 156 126 BYA 96 3 | |||
283 N/A 40 2 | |||
80 6 | |||
26 156 0 | |||
avs 96 3 | |||
283 II/A 41 2 | |||
82 5 | |||
26 130 0 | |||
Ave rage Avera ge Ave rage B rea ke r Total Years Cycles Cycles / | |||
Cycles / | |||
Se rvice | |||
/ Yea r Months 18 Months RTA 730 7 | |||
104.29 8.69 156.43 RTS 725 7 | |||
103.57 8.63 155.36 BYA 524 7 | |||
74.86 6.24 112.29 BYB 500 7 | |||
71.43 5.95 107.14 I | |||
r | r TABII 4 Reacter Trip Creaker Cyclo Estimat3 Us irHz 10 Trios Per Yea r CST 1.1.7 MSP 1.14 MSP 1.04.5 PMP Brechar S. aster Cycles Total htsbe r Cycles Total Number Cycles Total Numbe r Cycles Total Trips Tests / Test Cveles Tests | ||
TABII 4 Reacter Trip Creaker Cyclo Estimat3 Us irHz 10 Trios Per Yea r CST 1.1.7 | / Test Cveles Tests | ||
Se rvice | / Test Cycles Tests | ||
/ Test Cycles kA 15 3 | |||
e 1 | |||
8 8 | |||
9 3 | |||
27 1 | |||
26 26 15 RTS 15 3 | |||
45 1 | |||
8 8 | |||
9 3 | |||
27 1 | |||
26 26 15 BYA 15 3 | |||
45 N/A 9 | |||
2 27 1 | |||
26 26 0 | |||
BYS 15 3 | |||
45 N/A 9 | |||
2 27 1 | |||
26 26 0 | |||
Ave rage Ave rage Ave rage Breaker Total Yea rs Cycles Cycles / | |||
Cycles / | |||
Se rvice | |||
/ Yea r Months 18 Months RTA 121 1.5 80.67 6.72 121.00 RTB 121 1.5 80.67 6.72 121.00 BYA 89 1.5 59.33 4.94 89.00 BYB 89 1.5 59.33 4.94 89.00 l | |||
l l | l l | ||
l | l | ||
Figure 1 Beawee Walley Power Station Unit 1 Reactor Trips per Year Nam &ee of Trips 60 | l Figure 1 Beawee Walley Power Station Unit 1 Reactor Trips per Year Nam &ee of Trips 60 49 50 i | ||
50 | l m | ||
l m | |||
l l | l l | ||
30 | 30 29 l | ||
29 l | l 20 13 12 12 10 9 | ||
l | 7 4 | ||
13 | 0 1976 1977 1978 1979 1980 1981 1982 1983 1984 Year | ||
1976 1977 | |||
FIGURE 2 MAIN REACTOR TRIP BREAKER "A" TIME RESPONSE Time te initiate (seconds) | FIGURE 2 MAIN REACTOR TRIP BREAKER "A" TIME RESPONSE Time te initiate (seconds) | ||
: 0. M | : 0. M Limit 0.1667 sec. | ||
0.1665 | 0.1665 O.1332 0.0999 0.0666 0.0333 0 | ||
O.1332 | fYllffsYffkYlfl$lfkhflff DATE MAIN REACTOR TRIP BREAKER "B" TIME RESPONSE Time to initiate (seconds) 0.1998-Limit 0.1667 sec. | ||
0.0999 | O.1665 O.1332 0.0999 0.0666 l | ||
0.0666 | 0.0333 0 | ||
0.0333 0 | ^^-------------- | ||
fYllffsYffkYlfl$lfkhflff DATE MAIN REACTOR TRIP BREAKER "B" TIME RESPONSE Time to initiate (seconds) 0.1998- | |||
Limit 0.1667 sec. | |||
O.1665 | |||
O.1332 | |||
0.0999 0.0666 | |||
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Revision 1 | |||
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FIGUREh | FIGUREh | ||
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' ISSUE 1 i l | |||
REVISION l 1}} | |||
Latest revision as of 16:04, 12 December 2024
| ML20127K612 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/17/1985 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, TAC-53114, NUDOCS 8506270506 | |
| Download: ML20127K612 (22) | |
Text
QVg
'A@
Telephone (412) 393-6000 Nuclear Group
[$,,87,p*,,,,p4,3377. coa 4 June 17, 1985 Division of Licensing U.S. Nuclear Regulatory Commission Attn: Steven A. Varga, Chief Operating Reactors Branch No.1 Division of Licensing Washington, DC 20555
Reference:
Beaver Valley Power Station Unit No. 1 Docket No. 50-334, License No. DPR-65 Preliminary Safety Evaluation on Generic Letter 83-28, Itun 4.2.1 Gentlemen:
By letter dated April 24, 1985, the NRC provided a Preliminary Safety Evaluation (SE) on Generic Letter 83-28, Items 4.2.1 and 4.2.2, based on our November 4, 1983 and October 30, 1984 submi ttals.
The Preliminary SE concluded that our position on Item 4.2.2 is acceptable, however, our position on Item 4.2.1 requires additional justification for the 18-month preventive maintenance frequency on the reactor trip breakers.
As stated in our October 30,1984 submittal, we based the 18-month frequency on acceptable perfonnance and results from prior preventive maintenance, surveillance testing, and reactor trips.
To elaborate on this, the attached tables and figures sumuarize the history of the reactor trip breakers.
Table 1 summarizes the repairs perfonned on each breaker. As indicated in the table, most of the repairs involved either the circuit or main contacts. Only one repair required maintenance on the UVTA and in this case it was because the UVTA would not allow the breaker to stay closed.
Table 2 provides an estimate of past cycle history for the period 1975 thru June 1, 1983.
p p
,' t pg#WMr e
I Braver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 Preliminary Safety Evaluation on Generic Letter 83-28, Item 4.2.1 Page l Tables 3 and 4 provide estimates of expected breaker cycles using the testing criteria that resulted from the Salem ATWS event.
Table 3 uses l
the test and trip data that occurred in the period 1975 thru June 1,1983; while Table 4 is based on 10 reactor trips per year.
In both estimates, 200 breaker cycles are not exceeded in an average 18-month period.
Figure 1 shows the number of reactor trips per year and indicates a decrease to below 10 trips per year.
Figures 2 thru 16 summarize the trended parameters with data dating i
back to 1976 for some parameters.
I In summary, we believe that the infonnation provided in this submittal justifies our position regarding the frequency for preventive maintenance on reactor trip breakers, t
If you have any questions regarding this infonnation, please contact my office.
l Very tru y yours, J.
. Carey l
Vice President i
Nuclear Group Attachments: Tables 1 thru 4 f
Figures 1 thru 16 cc: Mr. W. M. Troskoski, Resident Inspector U.S. Nuclear Regulatory Connission Beaver Valley Power Station Shippingport, PA 15077 U.S. Nuclear Regulatory Canmission
[
c/o Document Management Branch Washington, DC 10555 l
Direc. tor, Safety Evalaution & Control Virginia Electric & Power Company l
P.O. Box 26666 One James River Plaza Richmond, VA 23261 l
I t
N i
e I
TABLE 8 Reactor Trio /Byoass Repairs e
MWR grea ke r Cate Feesir Reason Detection CTA 1/7/82 Replaced Main Contacts Main Contacts out Preventive 826451 of limits.
Maintenance 8/22/83 Check out ok Breaker would not Time Response 837717 and cycled, close.
Test.
11/06/84 Replaced Aut. Switch Aux. Switch Contacts Preventive 848322 Assembly.
Burnt & Pitted Maintenance 12/24/84 Adjusted UVTA Breaker would not Su rve i l la nce 843056 Stay closed 843136 RTS 1/13/82 Replaced Main contacts Loose Contact Surfaces Preventive 826454 Maintenance CvA 3/6/82 Adjusted Main Contacts M$in Contacts out of Preventive 826464 Limits Maintenance 8/10/32 Replaced fuse and adjusted Blowing control power Surve i l la nce 822039 lever on X relay Fuse 822893 BY3 5/23/80 Replaced closing coil Breaker would not Surveillance 800687 stay closed 1/15/82 Replaced Phase 8 Main Contacts out Preventive 826455 Main contacts. Mjusted cf Limits.
Maintenance Phase A h C
]
i 6/4/82 Cleaned Closing Coit Breaker would not Surveillance 821161 Stay Closed 11/26/32 Replaced fuse and Blowing Control Powe r Surveillance 822893 adjusted lever on fuse 822039 X relay 9/13/83 Replaced Control Relay Control Relay housing Su rve i l la nce 831688 i
b roken 10/12/83 No problem found Breaker would not Surveillance 832074 close I
i 10/17/83 Replaced Control Relay Relay Broken 837573 j
I l
._,_,s_.
TABLE 2 RecctOr Trip Creaker Cyclo CICtery a s o f J urie 1.
1983 CST 1.1.7 MSP 1.14 MSP 1.04,5 PMP Sma ke r Ester Cycles Total mer Cycles Total Rumber Cycles Total Nuebe r Cycles Total Trips Dsts /fest Cvetes Tests
/ Test Cvele_1 Tests
/ Test Cveles Tests
/ Test Cveles RIA 96 2
192 5
4 20 40 1
40 6
7 42 126 RTS 2
192 4
4 16 41 1
41 6
7 42 126 B~r A 96 1
96 N/A 40 1
40 6
7 42 0
frv3 96 1
96 N/A 41 1
41 5
7 36 0
Ave rage Ave rage Ave rage Breake r Total Yea rs Cycles Cycles /
Cycles /
Se rvice
/ Year Months 18 Months RTA 420 7
60.00 5.00 90.00 RTS 417 7
59.57 4.96 89.36 BYA 178 7
25.43 2.12 38.14 BYB 172 7
2f.57 2.05 36.86 4
l l
l I
l
r TASLE 3 Reacter Trip Creaker Cyclo Ettimate U,i ne Pa s t Test History i
CST 1.T.7 MSP 1.14 MSP 1.04.5 PHP l
Bresher taber Cycles Tctal numbe r Cycles Total Numbe r Cycles Total alumbe r Cycles Total Trips Tests / Test CWies Tests
/ Test Cycles Tests
/ Test Cveles Tests
/ Test Cycles RfA 96 3
258 8
40 40 3
120 6
26 156 126 l
RTS 96 3
253 4
8 32 41 3
123 6
26 156 126 BYA 96 3
283 N/A 40 2
80 6
26 156 0
avs 96 3
283 II/A 41 2
82 5
26 130 0
Ave rage Avera ge Ave rage B rea ke r Total Years Cycles Cycles /
Cycles /
Se rvice
/ Yea r Months 18 Months RTA 730 7
104.29 8.69 156.43 RTS 725 7
103.57 8.63 155.36 BYA 524 7
74.86 6.24 112.29 BYB 500 7
71.43 5.95 107.14 I
r TABII 4 Reacter Trip Creaker Cyclo Estimat3 Us irHz 10 Trios Per Yea r CST 1.1.7 MSP 1.14 MSP 1.04.5 PMP Brechar S. aster Cycles Total htsbe r Cycles Total Number Cycles Total Numbe r Cycles Total Trips Tests / Test Cveles Tests
/ Test Cveles Tests
/ Test Cycles Tests
/ Test Cycles kA 15 3
e 1
8 8
9 3
27 1
26 26 15 RTS 15 3
45 1
8 8
9 3
27 1
26 26 15 BYA 15 3
45 N/A 9
2 27 1
26 26 0
BYS 15 3
45 N/A 9
2 27 1
26 26 0
Ave rage Ave rage Ave rage Breaker Total Yea rs Cycles Cycles /
Cycles /
Se rvice
/ Yea r Months 18 Months RTA 121 1.5 80.67 6.72 121.00 RTB 121 1.5 80.67 6.72 121.00 BYA 89 1.5 59.33 4.94 89.00 BYB 89 1.5 59.33 4.94 89.00 l
l l
l
l Figure 1 Beawee Walley Power Station Unit 1 Reactor Trips per Year Nam &ee of Trips 60 49 50 i
l m
l l
30 29 l
l 20 13 12 12 10 9
7 4
0 1976 1977 1978 1979 1980 1981 1982 1983 1984 Year
FIGURE 2 MAIN REACTOR TRIP BREAKER "A" TIME RESPONSE Time te initiate (seconds)
- 0. M Limit 0.1667 sec.
0.1665 O.1332 0.0999 0.0666 0.0333 0
fYllffsYffkYlfl$lfkhflff DATE MAIN REACTOR TRIP BREAKER "B" TIME RESPONSE Time to initiate (seconds) 0.1998-Limit 0.1667 sec.
O.1665 O.1332 0.0999 0.0666 l
0.0333 0
^^--------------
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