ML20076G319
| ML20076G319 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/07/1983 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| REF-SSINS-6020 IEB-83-03, IEB-83-3, NUDOCS 8306140620 | |
| Download: ML20076G319 (8) | |
Text
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Telephone (412) 4564000 Nuclear Division P.O. Box 4 shippingport, PA 150774004 U. S. Nuclear Regulatory Commission Of fice of Inspection 6 Enforcement A t tn : Acting Regional Administrator Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Reference:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 IE Bulletin 83-03 Centlemen:
We have reviewed IE Bulletin 83-03, " Check Valve Failures in Raw Water Cooling Systems of Diesel Generators". Attached is the information requested by Action Items 1, 2, 3, and 4 of the Bulletin.
The remaining information required by Action Item 5 will be submitted at a future date in accordance with the requirements of the Bulletin.
Please note that we intend to perform the valve integrity verifica-tion procedures at the frequencies listed in Table 1, which are more limiting than the requirements of the IST program listed in Attachment 2.
Our estimate of the manpower expended in conducting the review and preparing this response is 170 manhours.
If you have any questions concerning this response, please contact my cffice.
Very tr y yours, J.
. Carey Vice President, Nuclear cc:
Mr. W. M. Troskoski, Resident Inspector
- b. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555 i
8306140620 830607 I
PDR ADOCK 05000334 4
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o COMMONWEALTH OF PENNSYLVANIA)
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COUNTY OF BEAVER
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On this
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day of
, /fd8
, before IL4/d 7/A,#N/mtL/, a Notary Public in and for sa_id Commonwealth me, and County, personally appeared J. J. Carey, who being dulfiworn, deposed, and said that (1) he is Vice President of Duquesne Light, (2) he is duly authorized to execute and file the foregoing Submittal on behalf of said Company, and (3) the statements set forth in the Submittal are true and correct to the best of his knowledge, information and belief.
4.) N W
SHE44A N. TAT 14AE. NOTAny PustlC snappte8PGAI 8000, NAVER COUNTY gV COMul5$408 ERPitES SEPT.16,1985 membes. peassylvanie Association of Notaries -
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COMMONWEALTH OF PENNSYLVANIA)
) SS:
COUNTY OF BEAVER
)
On this
[
day of h h
, /'fd8
, before ILdtf 7N.,#/N, a Notary Public in and for said Commonwealth me, and County, personally appeared J. J. Carey, who being du19'iworn, deposed,-
and said that (1) he is Vice President of Duquesne Light, (2) he is duly-authorized to execute and file the foregoing Submittal on behalf of said Company, and (3) the statements set forth in the Submittal are true and correct to the best of his knowledge, information and belief.
d) /O-w SMEA N. FAT 104(, NOTA 4V PuttlC
$NIPMcGPeti 8000. KAVE# COUNTY av C0est$540s ERPtKS 54PT.16,1985 Membes Pesespoone Associatie of Netuies l
I
s ATTACHMENT 1 Response to IE Bulletin 83-03 Item 1 Licensees are requested to reviek'the plant Pump und Valve In-Service Test (IST) program required by Section XI of the ASME Boiler and Pressure Vessel Code and modify it if necessary to include check velves in the flow path of cooling water for the diesel generators from the intake to the discharge. Those portions of2 the cooling water system which do not directly supply the diesel may be excluddd from this review.
For example, if the cooling water to the diesci is supplied by the normally operating service water system,the -
loop of piping to the diesel from the service water piping and back must be considered, but not the complete service water system. :For 4
thoic cooling water systems which come into operation only upou demand for diesel cooling, all portions of the system which' are <
required to change state must be reviewed.
,/
Response
The Pump and Valve In-Service (IST) Program has been revikWed to determine if it includes all the check valves in the f1,ow path of d
cooling water to the diesel gererators cooling system heat ex-changers. Nine valves are cons'idered applicable to this bulletin, j
seven of which are already 'part iof the,IST Program. The ather two valves have been added to the program. Table 1 lists'.411 nine s'
e 1
of these check valves. The check 5
water system are not considered ap; valves in the auxiliary 'risc'r plicable to this bulletin since this system is not the norral'flowpath for cooling water to the diesel generators cooling saten haat exchangers.
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Item 2 r
For the valves described in '(1) above,,, licensees are requested to examine the IST program and mod,1fy it if necessary to include veri-fication procedures that confirm' the integrity of the valve internals.
This may be accomplished by usingl Loth a forward flow and a back flow test or by valve disassembly and inspection. Other equally effective means of assuring integrity of the valves may je, used. A i'
reasonabic schedule for the test lcf, these valves shall airo be in-cluded in the IST program.
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Response
i The IST-Program' hae,been modified (Attachment 2) to include verifica-
. s tion procedurea that confirm the integrity of the valve internals as listed in Table 1.
Three of the check valves will be tested by performing forward and reverse flow tests. The remaining six will be' disassembled and inspected to confirm the integrity of the valve inte rnals. The IST Progras modifications include the frequency schedule for testing.
17 1
s At tJchment,1 e.
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R:spon s to IE Bulletin 83-03
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Pcgn 2 1)
Item 3 ',' -
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f Licenseer are requested to perform initial valve integrity veri-
~fication' procedures for the valves identified in (1) above using the methods described in (2) above, to be completed by the end of the next refueling outage commencing af ter April 1,1983.
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1 Response m
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(The initial valve integrity verification will be performed for the check valves listed in Table 1 during the third refueling outage,
' ' scheduled to begin June 11, 1983, with the exception of valves
+
(RW-110, 111, 112 and 113]. These four valves will be replaced g 'as part of Design Change Package 369 and will be installed at the first scheduled outage af ter January,1984 which accommodates the required work.
Since these valves are scheduled for replacement and were just installed in 1980, they will not be checked during this outage.
Item 4 Licensees are requested to submit a report to the NRC within 90 days of the date of this bulletin, which lists the valves identified in (1) above and describes the valve integrity verification pro-cedure methods and schedule identified in (2) above. This report should include the history of any known previous failures of these valves at your plant.
f
Response
Table 1 lists the check valves applicable to Item 1 and describes the valve integrity verification procedure methods and a schedule for testing in accordance with Item 2.
Previous failures of these valves have occurred and are documented in LER 80-27.
The LER reported that during maintenance of a diesel generator cooling water heat exchanger, the internals of a river water flapper-type check valve were discovered in the cooler. The valve failure was caused by a combination of corrca *a=
of the carbon-steel valve and valve flutter.
In September, 198e.
flar valves of this type were replaced with stainless steal valv, s Item 5 Licensees are requested to submit a report to the NRC within 90 days of completion of the results of the initial valve integrity verifica-tion procedure performed in accordance with (3) above. For those valves which are found to have undergone either partial or complete disassembly of valve internals, a description of the failure mode should be included.
Response
The results of the initial valve integrity verification procedures to be performed during the third refueling outage will be reported within 90 days of completion of the results.
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Attechment 1 Recpon2a to IE Bulletin 83-03 Pegs 2 Item 3 Licensees are requested to perform initial valve integrity veri-fication procedures for the valves identified in (1) above using the methods described in (2) above, to be completed by the end of the next refueling outage commencing af ter April 1,1983.
Response
The initial valve integrity verification will be performed for the check valves listed in Table 1 during the third refueling outage, scheduled to begin June 11, 1983, with the exception of valves
[RW-110,111,112 and 113]. These four valves will be replaced as part of Design Change Package 369 and will be installed at the first scheduled outage af ter January,1984 which accommodates the required work.
Since these valves are scheduled for replacement and were just installed in 1980, they will not be checked during this outage.
Item 4 Licensees are requested to submit a report to the NRC within 90 days of the date of this bulletin, which lists the valves identified in (1) above and describes the valve integrity verification pro-cedure methods and schedule identified in (2) above.
This report should include the history of any known previous failures of these valves at your plant.
_ Response Table 1 lists the check valves applicable to Item 1 and describes the valve integrity verification procedure methods and a schedule for testing in accordance with Item 2.
Previous failures of these valves have occurred and are documented in LER 80-27.
The LER reported that during maintenance of a diesel generator cooling water heat exchanger, the internals of a river water flapper-type check valve were discovered in the cooler. The valve failure was caused by a combination of corrosion of the carbon-steci valve and valve flutter. In September, 1980, similar valves of this type were replaced with stainless steel valves.
Item 5 Licensees are requested to submit a report to the NRC within 90 days of completion of the results of the initial valve integrity verifica-tion procedure performed in accordance with (3) above.
For those valves which are found to have undergone either partial or complete disassembly of valve internals, a description of the failure mode should be included.
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i
Response
The results of the initial valve integrity verification procedures to be performed during the third refueling outage will be reported within 90 days of completion of the results.
TABLE 1 Valve Integrity Verification Methods Valve No.
Forward Reverse (UFSAR Flow Test Frequency Flow Test Frequency Fig. No.)
1RW-106 OST 1.30.2 Monthly Disassemble and In-40 months (9.9-1A) spect in conjunction with the ISI hydro on buried River Water lines 1RW-107 OST 1.30.3 Monthly Disassemble and In-40 months (9.9-1A) spect in conjunction with the ISI hydro on buried River Water lines ikW-110*
OST 1.36.1 Monthly Disassemble & Inspect 5 yrs.
(9.9-1A)
OST 1.36.1 Monthly Disassemble & Inspect 5 yrs.
(9.9-1A)
OST 1.36.2 Monthly Disassemble & Inspect 5 yrs.
(9.9-1A)
- OST 1.36.2 Monthly Disassemble & Inspect 5 yrs.
(9.9-1A)
OST 1.30.2 Monthly OST 1.30.3 and 6 Monthly (9.9-1B) 1RW-58*
OSI 1.30.3 Monthly OST 1.30.2 and 6 Monthly (9.9-1B) 1RW-59*
OST 1.30.6 Monthly OST 1.30.2 and 3 Monthly (9.9-1B)
Valves previously in the IST Program a
ATTACliMENT 2 MANUAL NUMBER 30 PAGE 49 SYSTi}l NA!!E River Water e
a mE b
u Valve m
Ca tego ry Jg Jq y
yg Mark e
$j Eo N5 N 5-Number g
Type y
y2 y8 gj jj Testing and Tracking A
B C
D E
1RW57 3
X VCI15C RM127B F-2 Q
OST 1.30.2 - Monthly Test $ f3k3 P
1RW58 3
X VCT15C RM127B F-3 Q
OSi
$0I2 US1' E"
USTdtQ3072 Y
' ""d P"
1RW59 3
X VCI15C RM127B F-4 Q
o 1RW60 3
X, X
WF15A LS RM127B E-4 Q
OST 1.47.3A (Unit 2 Supply)
I 1RW61 WF15A S
RM127B E-2 NSR - OST 1.1.9 - Refueling stroke l
1RW98 3
X X
VBS15C LS RM127B D-3 Q
OST 1.47.3A (Unit 2 Supply) 1RW101A 2
X RV RM127B D-1 ST Tested per independent laboratory 1RW101B 2
X RV RM127B E-1 ST Tested per independent laboratory
~V RM127B F-1 ST Tested per independent laboratory R
1RW101C 2
X 1RW101D 2
X RV RM127B F-1 ST Tested per independent laboratory l
1RW102A 3
X RV RM127B B-3 ST Tested per independent laboratory f
OST 1.47.3A - Quarterly stroke and time 1RW102A1 3
X MOV S
RM127B F-2 g
IRW102A2 3
X MOV 0
RM127B F-2 Q
OST 1.47.3A - Quarterly stroke and time IRW102B 3
X RV RM127B B-3 ST Tested per independent laboratory 1RW102B1 3
X MOV S
RM127B F-3 Q
OST 1.47.3A - Quarterly stroke and time IRW102B2 3
X MOV S
RM127B F-3 Q
OST 1.47.3A - Quarterly stroke and time IRW102C 3
X RV RM127B C-3 ST Tested per independent laboratory 1RW102C1 3
X MOV S
RM127B F-4 Q
OST 1.47.3A - Quarterly stroke and time IRW102C2 3
X MOV S
RM127B F-4 Q
OST 1.47.3A - Quarterly stroke and time IRW103A 3
X MOV S
RM127A D-4 Q
OST 1.30.4 - Monthly stroke and time
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53 SYSTEN NAME River Water MANUAL NUMBER 30 PAGE E
c u
e alve
,g g
y Valve Category Jy Jg g
yy Mark m
Ej E$
E NS Number E
g Type y
gg
- g 6
'y y yy Testing and Tracking A
B C
D E
1RW221 3
.X VCIl5C RM247 E-3 Q
OST 1.30.lA - Monthly Stroke 1RW222 3
X VCIl5C RM247 E-4 Q
OST 1.30.lB - Monthly Stroke 1RW275 N
X VGW15A LO RM127C E-3 Locked or scaled valve log 1RW276 N
X VGW15A LO RM127C E-4 Locked or sealed valve log 1RW2'77 3
X VCW15A RM247 E-3 Q
OST 1.30.lA - Monthly stroke l'RW278 3
X VCW15A RM247 E-4 Q
OST 1.30.lB - Monthly stroke 1RW481 3
X VGW15A LO RM127B F-2 Locked or. sealed valve log 1RW482 3
X VGW15A LO RM127B:
F-3 Locked or sealed valve log 1RW433 3
X VGW15A Lo RM127B F-4.
Locked or scaled valve log 1RW4d4 3
VGW15A LO RM127B F-5 NSR - Locked or sealed valve log 1RW485 3
VGW15A LO RM127B F-5 NSR - Locked or sealed valve log i
1RW486 3
X VCW60A RM127B F-2 OST 1.30.2 - Monthly stroke and 1
Backseat per OST 1.30.3 i
1RN487 3
X VCW60A RM127B F-3 OST 1.30.3 - Monthly stroke and I
Backseat per OST 1.30.2 1
1 1RW488 3
X VCW60A RM127B F-4 OST 1.30.6 - Monthly stroke and I.
Backseat per OST 1.30.2
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6-8-83
SYSTDI NAME River Water MANUAL NUMBER 30 PAGE 53a a
e mE O
u Valve u
Category cy Cy 3
ya Mark m
N$
$o mE U 5' Number g
Type g
gj g8 yy yj Testing and Tracking A
B C
D E
X VCI-15C RM127 F-5 Q
OST 1.36.1 and Internal Inspection 1.75.18e IRW-111 3
X VCI-15C RM127 F-5 Q
05[f:3h:fggndInternalInspectionper 1RW-ll2 3
X VCI-15C RM127 G-5 Q
8MJf:3h: 2 gnd internal Inspection per g
OST 1.36.2 and Internal Inspection per 1RW-l'13 3
X VCI-15C RM127 G-5 Q
X RM127 F-8 M
Forward Flow OST 1.30.2 Reverse Flow in Conjunction with RW llydro 1RW-107 3
X RM127 F-8 M
Forward Flow OST 1.30.3 Reverse Flow in Conjunction with RW liydro 6-8-83