ML20073C430
| ML20073C430 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 09/16/1994 |
| From: | Feigenbaum T NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-89-10, NYN-94106, NUDOCS 9409230322 | |
| Download: ML20073C430 (8) | |
Text
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4 North Atlantic Energy Service Corporation C
1 NortLit y.o. ne, 300 Atlantic se broex = o3874 (603) 474-9521, Fax (603) 474-2987 o
The Northeast Utilities System Ted C. Feigenbaum NYN-94106 Senior Vice President &
Chief Nuclear Officer September 16,1994 United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention:
Document Control Desk
Reference:
(a)
Facility Operating License No. NPF-86, Docket No. 50-443 (b)
New liampshire Yankee letter NYN-90003 dated January 2,1990, " Response to Generic Letter 89-10", T.C. Feigenbaum to USNRC (c)
New 11ampshire Yankee letter NYN-920924 dated March 2,1992, " Motor Operated Valve Grouping, Selection, and Exclusion Criteria for Differential Pressure Testing", T.C. Feigenbaum to USNRC (d)
New ilampshire Yankee letter 'NYN-92058 dated April 30,1992, " Response to a Request for Additional information", T.C. Feigenbaum to USNRC (c)
USNRC Inspection Report 94-11, "Seabrook Motor-Operated Valve Inspection"
Subject:
Generic Letter 89-10, " Safety Related Motor-Operated Valve 'lestmg and Suneillance" Gentlemen:
North Atlantic Energy Service Corporation (North Atlantic) is committed to implementing a quality motor operated valve (MOV) program that ensures MOVs will operate under design basis conditions for the life of the plant and addresses the NRC guidance provided in Generic Letter 89-10, including its supplements. North Atlantic's current commitments regarding Generic Letter 89-10 are provided in Reference (b) and are further clarified in References (c) and (d).
Prior to Refueling Outage 03, which commenced on April 9,1994, we had intended to complete the initial cycle of testing in accordance with our Generic Letter 89-10 MOV Program during the outage.
l Ilowever, the feedback from the NRC obtained during the MOV Inspection which occurred at the i
beginning of the outage [ Reference (e)] indicated that our dynamic testing grouping methodology was deemed to be inconsistent with the guidance of Generic Letter 89-10, Supplement 6 (Supplement 6).
The grouping methodology for Seabrook Station's motor-operated valves was developed and submitted to the NRC prior to the NRC issuing the grouping guidance of Supplement 6 [ Reference (c)].
The initial NRC review of the dynamic testing grouping methodology was performed during the MOV inspection. This review identified that additional valves would have to be tested and the valve grouping l
methodology would have to be revised to address the guidance of Supplement 6.
l n n e t.n (; ~-
,l 9409230322 94o916 hDR ADOCK O=500o443 3
I' 1
United States Nuclear Regulatory Commission September 16,1994 l
Attention:
Document Control Desk Page two l
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During the MOV. inspection we agreed that North Atlantic would not respond to Supplement 6 until a management meeting had been held to review all the open MOV issues. This meeting was originally proposed for late August but the extended refueling outage precluded this meeting from being
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held. It is our understanding that the meeting will be held after the NRC conducts the Region i MOV l
Workshop in October. North Atlantic is submitting this letter to clarify the status of our MOV program l
and completion commitments.
North Atlantic has reviewed Supplement 6 and is presently reviewing the Seabrook MOV program I
to revise the grouping methodology and address the guidance of Supplement 6. Based on this review, we 1
have determined that MOVs can be placed in one of 33 groups vs 35 groups, as originally planned. This revised grouping will require the differential pressure testing of nine additional MOVs in order to fully implement the guidance of Supplement 6.
North Atlantic has completed the design basis review, performed diagnostic testing, and set the MOV switch setpoints in accordance with the design basis t
calculations for all 122 MOVs in the Seabrook MOV program. In addition, we have included all position-changeable MOVs in the Seabrook program. Figure 1 lists the groups that currently have differential pressure testing comple:ed in accordance with Supplement 6.
The nine additional valves and their characteristics are listed in Figures 2 and 3. Figure 2 lists the four of these nine valves that can be tested during cycle 4 with the plant on line. Figure 3 lists the five of these nine valves that can only be tested when the plant is shutdown. Testing of three of these five valves can only be performed when the plant l
is in Mode 6. One of the remaining two valves requires Mode 3 and the other requires Mode 4. We will l
l develop plans to test the two valves that require Mode 3/4 during cycle 4 if the required conditions I
become available because of a forced shutdown.
l Nonh Atlantic will complete the activities required to address Generic Letter 89-10, through Supplement 6 by the completion of Refueling Outage 04 which is currently scheduled to begin January 7,1996. We are also reviewing our MOV testing data and the relevant industry data and will revise our program to incorporate the appropriate material prior to the next cycle of dynamic testing. In addition, l
should the plant experience an unscheduled outage during cycle 4 that has the appropriate conditions to l
safely accommodate testing of MOVs we will perform such testing in the time available in the outage schedule. North Atlantic will provide a completion report to the NRC within 30 days of Refueling Outage 04.
l North Atlantic is monitoring NRC progress with Supplement 7 and will incorporate the applicable attributes into our MOV program. We will keep the NRC informed of any significant changes to our program as a result of Supplement 7, including a separate schedule for Supplemem 7.
I We look forward to discussing this issue and other issues identified in Inspection Report 94-11 during a meeting at your offices after the October Regional MOV Workshop.
Should you have any questions regarding this matter, please contact Mr. Terry L. Harpster, Director of Licensing Senices, at (603) 474-9521, extension 2765.
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Very truly yours,
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fG' a&v Ted C. Feigenbabt i
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a United States Nuclear Regulatory Commission September 16,1994 Attention:
Document Control Desk Page three TCF/JMP:sm cc:
Mr. Thomas T. Martin Regional Administrator U.S. Nuclear Regulatory Commission Region I 475 Allendale Road.
King of Prussia, PA 19406 Mr. Alben W. De Agazio, Sr. Project Manager Project Directorate 1-4 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Antone C. Cerne l
NRC Senior Resident inspector P.O. Box 1149 Seabrook, NH 03874 i
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P ge1 FIGURE 1 COMPLETED MOV DP TEST GROUPS DP DESCRIPTION NO TOTAL PERCENT NOTES TAGIDS TEST TESTED GRP 2
3 Westinghouse Gate 2
4 50 %
None 1-CS-V-143 SB-00 Limitorque Actuator 1-CS-V-142 Ileasy Spring Pack -
1-RC-V-124 15 Alb Motor 1-RC-V-122 5
4" Westinghouse Gate 4
7 57 %
Nonc l-SI-V-114 l
SB/Sh1B-00 Limitorque 1-SI-V-77 Actuator 1-SI-V-139 Ileasy Spring Pack 1-SI-V-112 15 filb hiotor 1-SI-V-111 1-SI-V-102 1-SI-V-138 7
6" Veian Gate 1
2 50 %
Although the percent completion for this group is 50% this is only a 1-FW-V-156 Sh18-0 Limitorque Actuator two vahr group. The vahr not tested in this group is a normally 1-FW-V-163 IIcasy Spring Pack closed isolation vahr in the crossconnect line beturen the startup 25 filb hiotor feed pump and the emergency feedwater supply header. This vahr is not required to open or close under differential pressure conditions. Baseline static diagnostic testing for both vahrs in this group has been satisfactorily completed. The vahr in this group that was tested under ditTerential pressure conditions tested satisfactorily at near full design dP and line pressure.
8 6" Westinghouse Gate I
i 100 %
Nonc l-CBS-V-53 Sh1B-000 Limitorque Actuator Extra Heavy Spring Pack 10 Alb hiotor 1I 8" Westinghouse Gate 2
2 100 %
None 1-RH-V-70 Sh1B-0 Limitorque Actuator 1-RH-V-32 Heasy Spring Pack 25 Illb hiotor 15 12" Westinghouse Gate 2
2 100 %
None 1-CBS-V-5 SB-1 Limitorque Actuator 1-CBS-V-2 Heavy Spring Pack 60 Rib hiotor
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b Pzge 2 FIGURE 1
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COMPLETED MOV DP TEST GROUPS DP DESCRIPTION NO TOTAL PERCENT NOTES TAG IDS TEST TESTED GRP 17 12" Velan Gate 1
2 50 %
Although the percent completion for this group is 50% this is only a 1-AS-V-176 SB-1 Limitorque Actuator two valve group. Both valves in tids group are auxiliary steam 1-AS-V-175 Light Spring Pack system high energy line break isolation valves. Differential 40 filb Motor pressure testing for the one vahr tested simulated a line break by way of a test line open to atmosphere. The flow achieved uns greater than 60,000 lbm/hr of 150 psig steam supplied by both auxiliary boilers. 'Dre vahr successfully cut off the 60,000 lbm/hr flow with sizable margin. The vahr stroke time is less than the -
time required for the mlume of steam in the downstream header to expand out of the line break. The result is a much smaller differential pressure than was conservatively assumed for these vahrs. Additional differential pressure testing for the second vahr would not produce meaningful test results. Baseline static diagnostic testing for both vahts in this group has been satisfactorily completed.
20 1" Yaruny Angled Globe 3
4 75 %
Nonc l-MSD-V-44 SMB-000 Limitorque Actuator 1-MSD-V-45 Heavy / Extra IIcary Spring 1-MSD-V-46 Pack 1-MSD-V-47 5 ftib Motor 26 4" Masoncilon Globe 3
3 37.5 %
None=
l-FW-FV-4234B NAl Rotork Actuator 1-FW-FV-4244A 11 Spring Pack 1-FW-FV-4244B 50 filb Motor 1-FW-FV-4214B l-FW-FV-4234A 1-FW-FV-4224B 6
1-FW-FV-4224A 1-FW-FV-4214 A
[
28 4" Velan Globe 2
2 100 %
Nonc l-FW-V-347 SMB-00 Limitorque Actuator 1-FW-V-346 IIcavy Spring Pack 10 filb Motor
Prge 3 FIGURE 1 COMPLETED MOV DP TEST GROUPS DESCRIPTION NO TOTAL PERCENT
' NOTES TAGIDS DP TEST TESTED GRP 29 6 Posi Seal Butterfly 4
4 100 %
Nonc l-CC-V-1101 SMB-000 Limitorque Actuator 1-CC-V-1092 Light Spring Pack 1-CC-V-1109 2 nib Motor 1-CC-V-1095 31 14"&l6" Posi Seal Butterfly 3
4 75 %
None I-CC-V-272 SMB-000 Limitorque Actuator 1-CC-V-266 Light Spring Pack 1-CC-V-145 5 filb Motor 1-CC-V-137 32 24' Fisher Butterfly 13 20 65 %
Nonc l-SW-V-31 SMB-0 Limitorque Actuator 1-SW-V-20 Light Spring Pack 1-SW-V-19 15 nlb Motor I-SW-V-17 1-SW-V-140 1-SW-V-23 1-SW-V-29 l-SW-V-34 1-SW-V-22 1-SW-V-2 1-SW-V-139 l-SW-V-76 1-SW-V-27 1-SW-V-54 1-SW-V-55 1-SW-V-56 1-SW-V-74 j
1-SW-V-25 l-SW-V-15 1-SW-V -;
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P4ge 1 FIGURE 2 MOV DP TESTS DURING CYCLE 4 PRIOR TO 7/1/95 VALVE ID DP PRA NAME DESCRIPTION DESIGN DATA NOTES TEST GRP l-CS-V-196 22 4
Charging Pump 2" Vclan/ Westinghouse Design Vah e Factor - Open = 1.103 This valve has low risk significance. Baseline (low
'A' Min Flow Globe Design Valve Factor - Close = 1.134 static diagnostic testing for both vahrs in this risk Isolation SMB-00 Limitorque Design DP - Open = 2745 psig group has been satisfactorily completed.
high Actuator Design DP - Close = 2670 psig dP)
IIcavy Spring Pack Design Flow = 60 gpm 10 filb Motor 1-CS-V-197 22 4
Charging Pump 2" Velan/ Westinghouse Design Vahc Factor - Open = 1.103 This valve has low risk significance. Baseline (low
- B' Min Flow Globe Design Vahc Factor - Close = 1.134 static diagnostic testing for both valves in this risk Isolation SMB-00 Limitorque Design DP - Open = 2745 psig group has been satisfactorily completed.
high Actuator Design DP - Close = 2670 psig dP)
Ilcary Spring Pack Design Flow = 60 gpm 10 illb Motor 1-RH-FCV-610 24 5
RHR Pump 'A' 3" Vclan Globc Design Valve Factor - Open = 1.1 This vahr has low risk significance. The (Iow Min Flow SMB-00 Limitorque Design Valve Factor - Close = 1.1 other valve in this test group has been risk Control Actuator Design DP - Open = 202.7 psig satisfactorily tested under differential pressure low Extra Light Spring Pack Design DP - Close = 183.3 psig conditions. Baseline static diagnostic testing dP) 10 filb Motor Design Flow = 600 gpm for both vahrs in this group has been satisfactorily completed.
1-SW-V-5 30 3
SW Train 'B' 12" Fisher Butterfly Design Valve Factor - Open = NA This vahr has high risk significance but has (high Isolation To SMB-00 Limitorque Design Vahc Factor - Close = NA low dP. The other vahr in this test group has risk Secondary Loads Actuator Design DP - Open = 132.6 psig been satisfactorily tested under differential low Extra Light Spring Pack Design DP - Close = 132.6 psig pressure conditions.14 of 22 SW system dP) 5 filb Motor Design Flow = 2326 gpm butterfly vahrs have been dP tested, (63.6%)
with no problems. Baseline static diagnostic testing for both vahrs in this group has been satisfactorily completed.
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PageI FIGURE 3 BIOV DP TESTS DURING OR04 VALVE ID DP PRA NAME DESCRIPTION DESIGN DATA NOTES TEST GRP l-CS-V-149 01 3
Regen HX Outlet To 3" Westinghouse Gate Design Valve Factor - Open =.5491 The valve in this group is the regenerative (Lmv Letdown IIX Sh1B-000 Limitorque Design Valve Factor - Close =.6713 heat exchanger isolation vahr to the risk Actuator Design DP - Open = 600 psig letdown heat exchanger. This vahr will be med Extra licasy Spring Pack Design DP - Close = 600 psig tested during the fourth refueling outage.
dF) 10 filb hiotor Design Flow = 120 gpm This valve has low risk significance.
Baseline static diagnostic testing has been satisfactorily completed.
1-Ril-V-22 09 6
RHR Train 'A' 8" Westinghouse Gate
. Design Valve Factor - Open =.670 The valves in this group are RHR isolation (Low Discharge Cross-ShiB-00 Limitorque Design Valve Factor - Close =.736 valves. One additional valve will be tested risk Connect Actuator Design DP - Open = 360.3 psig during the fourth refueling outage. The mis-hiedium Spring Pack Design DP - Close = 253.4 psig valves in this group have low risk pos 25 filb hiotor Design Flow = 2362 gpm significance. Baseline static diagnostic only) testing for all vahes in this group has been satisfactorily completed.
1-RH-V-26 12 4
RHR Train *B* To Cold 8" Westinghouse Gate Design Vahe Factor - Open =.5381 This valve has medium risk significance but (hied Legs 3 And 4 SB-1 Limitorque Actuator Design Valve Factor - Close =.6103 with low dP. The other vah e in this test risk Heasy Spring Pack Design DP - Open = 625 psig group has been tested under differential low 60 filb hiotor Design DP - Close = 190 psig pressure conditions. Baseline static dP)
Design Flow = 3500 gpm diagnostic testing for both valves in this group has been satisfactorily completed.
1-RC-V-323 19 3
Reactor 1Icad Vent 3/4" Velan Globe Design Vahe Factor - Open = 1.0 The valve in this group is a reactor srssel (Low Isolation ShfB-000 Limitorque Design Vahr Factor - Close = 1.1 head vent vahr and has low risk risk Actuator Design DP - Open = 2595 psig significance. The vahe is a normally closed high Extra Light Spring Pack Design DP - Close = 2595 psig globe valve in series with a normally closed dP) 2 filb Motor Design Flow = < chg pump make up solenoid operated globe valve both with pressure underneath the seat.
1-h1S-V-206 25 6
SG 'C' h1SIV Bypass 3" Velan Globe Design Vah e Factor - Open = 1.68 This vahc has low risk significance. The (Low ShfB-00 Limitorque Design Valve Factor - Close = 1.68 other valve in this test group has been tested risk Actuator Design DP - Open = 1236 psig under differential pressure conditions.
mis-Extra Light Spring Pack Design DP - Close = 1236 psig Baseline static diagnostic testing for both pos 10 filb hiotor Design Flow = 109000 lbm/hr vahrs in this group has been satisfactorily only) completed.
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