ML20076F834
| ML20076F834 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/04/1994 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18151A617 | List: |
| References | |
| PROC-940804-01, PROC-940804-1, NUDOCS 9410180169 | |
| Download: ML20076F834 (33) | |
Text
a-J N
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ATTACHMENT 2 CHANGES TO SURRY UNIT 2 THIRD INTERVAL INSERVICE TESTING PROGRAM REVISION O CHANGE 1 4
l 9410190169 943o11 DR ADOCK 05000280 PDR
4 ATTACHMENT
SUMMARY
OF CHANGES TO THE SURRY UNIT 2
~IST PROGRAM
- The following is a section by section summary of changes for Revision 0, Change 1 of the Surry Power Station Unit 2 Inservice Testing (IST) Program for the third IST interval.
Revision 0 for the third IST interval was submitted on October 19, 1993 (Serial
~
No.93-658).
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES 3.0 PUMP INSERVICE TEST PROGRAM DESCRIPTION 3.5 PUMP INSERVICE TEST TABLES Unit 2 Pump Number Procram Chance CC-P-2A Relief Request P-19 was added for the suction' 2-CC-P-2B pressure instrumentation.
3.6 PUMP TEST PROGRAM RELIEF REQUESTS Unit 2 Relief Recuest Procram Chance P-19 This relief reauest is beina added to the IST Proaram for the comoonent coolina water cumos 2-CC-P-2A and B.
Recently installed inlet pressure gauges have a full scale range of 0 to 3.5 psig.
Readings from these inlet pressure gauges over the past year indicate that the dynamic pressures fall I
within the bottom third of full scale.
- However, i
the difference in the error between the o to 3.5 l
psig gauges and gauges that would meet the ASME Section XI three times full-scale rule are so H
small that the o to 3.5 psig gauges can be considered to be equivalent in terms of accuracy for determining differential pressure.
Therefore, inlet pressure will be measured with gauges that 3
have a full-scale of 0 to 3.5 psig.-
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ATTACHMENT
SUMMARY
OF CHANGES TO THE I
SURRY UNIT 2
)
IST PROGRAM 3.7 ALTERNATIVE TESTING FOR NON-CODE PUMPS Unit 2 Non-Code Alternative TeFt Procram Chance PNC-1 Reference to the frequency response range of the vibration transducers was added, The minimum pump shaft rotational speed for the diesel fuel oil pumps is 690 rpm.
To meet the one-third shaft speed requirement, the low and of the frequency response range would have to be 3.8 hz.
The transducers used for testing the diesel fuel oil transfer pumps have a low and frequency response of 10 hz.
These transducers are capable of detecting vibrations at frequencies of at least one times the rotational speed of the pump, which is adequate for detecting degradation in positive displacement pumps.
A note indicating that OM Part 6 does not require the measurement of suction pressure for positive displacement pumps was added.
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ATTACHMENT
SUMMARY
OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM 4.0 VALVE INSERVICE TEST PROGRAM DESCRIPTION
'4.4 VALVE INSERVICE TEST TABLES Unit 2 valve Number Comment / Program Change 2-MS-NRV-201A Program Change:
The ASME Code Classification 2-MS-NRV-201B was changed from Class 2 to non-Code Class.
2-MS-NRV-201C 2-MS-TV-209 2-MS-TV-210 2-CH-LCV-2115B' As for Unit 1, these isolation valves prevent 2-CH-LCV-2115D leakage of contaminated containment sump 2-SI-25 water to the refueling water storage tank 2-SI-MOV-2885A from the discharge side of the low head 2-SI-MOV-2885B safety injection pumps during recirculation 2-SI-MOV-2885C mode transfer phase of safety injection.
2-SI-MOV-2885D Relief Request V-52 is being added to the IST program and states that in addition to replacement and repair as corrective actions, an evaluation can be performed.
Relief Request V-52 was sent to the NRC by letter dated April 26, 1994 (serial No.94-223) and is being included in the IST Program through' t
Change 1 to Revision O.
Program Change:
Relief Request V-52 is being added for the leak test.
2-SI-25 The test method to verify valve closure was changed from disassembly and inspection to back seat testing every reactor refueling.
Refer to Reactor Refueling Justification RVV-5.
Program Change:
Reactor Refueling Justification RRV-5 was revised.
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-ATTACHMENT l
SUMMARY
OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM 2-SI-107 These accumulator discharge check valves will 2-SI-109 be tested as-pairs to the closed position.
2-SI-128 Refer to Relief Request V-26.
2-SI-130 2-SI-145 Program Change:
Relief Request-V-26 was 2-SI-147 revised to indicate that valves 2-SI-107 and 109, and 2-SI-128 and 130, and 2-SI-145 and 147 will be tested as pairs of valves in.
i series to the closed position.
Also,; Cold
+
Shutdown Justification CSV-29 is no longer necessary for valves 2-SI-109, 130 and 147, and was deleted from the program.
2-SW-130 The internal parts were removed from this check valve.
Program Change:
The valve was removed from the IST program.
4.5 VALVE TEST PROGRAM RELIEF REQUESTS-Unit 2 Relief Recuest Proaram Chance
)
V-26 This relief request was revised to indicate that the accumulator discharge check valves will be.
tested as pairs of valves to~the closed. position.
Valves 2-SI-107 and 109, 2-SI-128 and 130, and 2-SI-145 and.147 perform as pairs of valves in series to isolate the accumulators from the reactor coolant system.
The downstream valves, 1-SI-109, 130 and 147 were previously chosen as-the isolation valves and were subject to back seat-tests while the other valves were considered as backup valves and were.not subject to back seat tests.
The other set of valves cannot be individually.back seated.with'the current piping configure. tion.
Testing experience has shown. that i
a severs water hammer can be produced'by attempting to individually test the downstream isolation valve.
Treating the check valves as a pair of isolation valves would eliminate the possibility of creating 5
-gr ATTACHMENT
SUMMARY
OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM a water hammer event through testing.
The accumulators have level indicators and high/ low tarck level alarms in the control room.
Therefore, during normal operation the accumulator level is conutantly monitored to ensure that one out of two.
check valves.is seated properly to prevent in leakage from the reactor coolant system.
V-50 Valve 2-SW-130 was removed from the relief request.
V-52 This relief reauest is'beina'added to the IST orocram for the RWST isolation valves.
The RWST isolation valves prevent leakage of contaminated.
containment sump water to the refueling water storage tank from the discharge side of'the low
' head safety injection pumps during the recirculation mode transfer phase of safety injection.
Relief Request V-52 states'that in addition to replacement and repair as corrective actions, an evaluation can be performed.
Relief Request V-52 was sent to the NRC by letter dated April 26,'1994 (Serial No.94-223) and is being included in the IST Program through Change 1 to Revision O.
4.6 VALVE TEST PROGRAM COLD SHUTDOWN JUSTIFICATIONS Unit 2 Cold Shutdown Just Procram Chance CSV-29 This cold shutdown justification is being deleted from the IST program.
The accumulator discharge.
check valves will be tested as pairs to the' closed position per Relief Request V-26.
6
ATTACHMENT
SUMMARY
OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM' 4.7 VALVE TEST PROGRAM REACTOR REFUELING JUSTIFICATIONS Units 2 Reactor Refuel
)
Just Procram Chance RRV-3 Justification was added for not performing a partial stroke test on the accumulator discharge check valves during cold shutdowns.
RRV-5 Reactor Refueling Justification-RRV-5 was revised to indicate that 1-SI-25 (Unit 1) and 2-SI-25 (Unit 2) will be back seat / leak tested to verify closure every reactor refueling instead of disassembled and inspected.
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SURRY POWER STATION EXIT 2 REPLACEMENT PAGES t
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RELIEF REQUEST P-19
- I System :
Component Cooling Water I
Pump (s):
2-CC-P-2A 2-CC-P-2B Class 3
f i
OM Part 6 Code Requirements For Which Relief.Is Requested The full-scale range of each instrument shall be three times the reference value or less-(OM Part 6, Paragraph 4.6.1.2).
Basis For Reauest l
Recently installed inlet pressure gauges have a full scale range of 0 to 3.5 psig.
Readings from these. inlet pressure gauges over the past year. indicate that-the dynamic pressures fall within the H
i bottom third of full scale.
However, the difference in the error g!
between the o to 3.5 psig gauges and gauges that would meet the
.g three-times full-scale rule are so small that the o to 3.5 psig gauges can be considered to be equivalent in terms of accuracy for determining differential pressure.
For example, the lowest' recorded inlet' pressure for pump 2-CC-P-2A is 0.5 psig.-
A gauge that meets the three times full-scale rula would have a full scale of 1.5 psig or less.
A 2% accuracy j
for the 1.5 psig gauge translates to an error of 0.03 psig.
A 2%
accuracy for the 3.5 psig gauge translates to an error of 0.07 i
psig.
The difference in error of-0.04 psig'is insignificant when-determining the' differential' pressures'for-these pumps which range between 50 and 60 psig.- Therefore, the two gauges can be l
considered to be equivalent in terms of accuracy for determining differential pressure.
Alternate Testina Proposed i
Inlet pressure will be measured with gauges that have a full-j scale of 0 to 3.5 psig.
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3-20a Revision 0 l
S2PVI3RO' August 4, 1994 i
+ = =
-m!
a b-
j
- NON-CODE ALTERNATIVE TESTING PNC-1 i
i System :
Fuel Oil-i Pump (s):
1-EE-P-1B 1-EE-P-1E l
f Class NC OM Part 6 Code Requirements Which Cannot Be Met Measure test quantities after the pump has been running for at least two minutes (OM Part 6, Paragraph 5.6).
i i
The~ frequency response range of the vibration measuring l
transducers and their readout system shall be from one-third 1
minimum pump shaft rotational speed to at-least 1000 HZ (OM Part 6, Paragraph 4.6.1.6).
l Basis For Alternate Testina The pump operating time is limited due to operational restraints.
While the diesels are running, these pumps start automatically when the fuel oil level in the day tank reaches the low level-i switch, and stop when the level reaches the high level switch.
The pump run time can vary depending upon the diesel load'and the l
resulting fuel consumption rate.
If the pumps are allowed to run-for two. minutes prior to measuring the test quantities and the i
fuel consumption rate is low, not enough time is available to j
gather all of the required Section XI test data.
ri The minimum pump shaft rotational speed for these pumps is 690 rpm.
To meet the one-third shaft speed requirement, the low and of the frequency response range would have to be'3.8 hz.
The g
transducers used for tacting the diesel fuel oil transfer pumps'-
d' j have a low and frequency response of 10 hz.
These transducers are capable of detecting vibrations at frequencies of at least U
one times the rotational speed of the pump, which is adequate for detecting degradation in positiva displacement pumps.
Alternate Testina l
The measurement of Section XI quantities will begin when the pump automatically starts on a low tank level signal.
4 The transducers used for testing the diesel fuel oil transfer pumps have a low and frequency response of 10 hz versus the 3.8 2
i hz required by the Code for a pump running at 690 rpm.
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3-22 Revision 0 S2PVI3R0 August 4, 1994
="o
6
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NON-CODE ALTERNATIVE TESTING PNC-1 (Cont.)
H Note:.The diesel oil transfer pumps are positive displacement g-pumps.
According to OM Part 6, Table 2, only discharge pressure o
need be measured for positive displacement pumps.
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l 3-23 Revision 0 S2PVI3R0 August 4, 1994
VIRGINIA POER CEMPANY PAGE:
8 0F 66 SLAtRY UNIT 2 REVIsl0N: 00 TNIRD INSERVICE TESTING INTERVAL DATE: 08/04/94 INSERVI K TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASE IW VALVE YEST TEST REO JUST JUST TEST NUMBER NLMBER NLMBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-RRV VCN-
"C" CHARGING PLSF DISCNARGE RECIRC LINE CNEK VALVE 2 CH.276 11543-CBM 0BR3 2 0F 2 D-4 C K K VALVE 3.000 2 C
CV C
J 1
"C" CHARGING PLMP DISCNARGE CNEK VALVE 2-CM-309 11548-CsM-088C 10F2D4 CNE K VALVE 3.000 2 AC CIV CV C
6 LT C
MAIN CNARGING BUPPLY llEADER, INSIDE CONTAIN-MENT aSQLATIOli CNE N VALVE 2-CH-FCV-2113A 11548 cam 088B 1 0F 2 C 3 A0 GLOBE 1.000 2 B
EV O
FS 0
ST 0
VP GC MANUAL EE RGENCY BORATION PATM FLOW CONTROL VALVE 2-CM-FCV-2114A 11548 Cam 08as 1 0F 2 D.4 A0 GLOBE 2.000 2 5
EV C
FS C
ST C
VP OC PRIMARY GRADE WATER SUPPLY TO BORIC ACID SLENDER ISOLATION VALVE 2-CH FCV-2160 11548 CBM 088C 1 0F 2 5 4 A0 GLOSE 2.000 1 AE CIV LT C
VP GC CHARGING FLOW CONTROL 70 LOOP FILL NEADER.
DUTSIDE CONTAINMENT ISOLATION VALVE 2-CM-LCV 21158 1048 cam 0888 2 0F 2 B-8 No GATE 8.000 2 A
EV C
0 LT C
52 Q
ST C
Q 0
VP OC IEARGING PLMP SUPPLY ISOLATION VALVE FROM hEFUELING WATER STORAGE TANK 2-CH L*V 2115C 11548-CaN-0&B8 1 0F 2 Ca6 No GATE 4.000 2 8
EV C
11 ST C
11 VP OC CHARGING PLMP SUPPLY ISOLATION FROM VOLUME CONTROL TAmt 2 CM-LCv-21150 11548-Cam +0888 2 0F 2 C-8 No GATE 8.000 2 A
EV C
w4 0
LT C
52 Q
ST C
(j 0
VP GC
VIRGINIA P0bER COMPANY PAGE:
33 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 08/04/94
~
INSERVICE TESTING PROGRM. VALVE TABLE
+
NC ISO REL CS RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE AsnE IW VALVE TEST TEST REG JUST JUST TEST NUMBER NUMBER NUMBER C00R TYPE
$!ZE cLA e CAT TYPE TYPE POS V-CSV RRV-VCN-2 Ms-087 11548 CsM 064A 1 0F 6 C 6 MANUAL GATE 4.000 2 B
EV C
MAIN STEAM LINE To TUA3!NE DR4 WEN AUKILIARY FEEDWATER PlatP ISOLATION VALVE 2 Mi ' 20 11548 CSM 064A 2 0F 6 C 6 MANUAL GATE 4.000 2 B
EV C
MAIN STEAM LINE TO Tuts 1NE DRIVEN AUKILIARY FEEDWATER PUMP ISOLATION VALVE 2 MS 158 11548-CeM-064A 3 0F 6 C.6 MANu4L GATE 4.000 2 B
EV C
MAIN STEAM LINE TO TURBINE DRIVEN AUKILIART FEEDWATER PUMP ISOLATION VALVE 2 Ms 176 11548 Cam-064A 4 0F 6 C-7 CNECK VALVE 3.000 2 C
CV C
42 0
42
- A" MAIN STEAM NEADER SUPPLY CNECK VALVE TO TURBINE DRIVEN AUKILIARY FEEDWATER PtseP 2-Ms 178 11548-CSM 064A 4 0F 6 D-7 CNECK VALVE 3.000 2 C
cv c
42 0
42 "B" MAIN STEAM NEADER SUPPLY CNECK VALVE TO TURBINE DRIVEN AUKILIARY FEEDWATER PLSIP 2-MS 182 11548 cam-064A 4 0F 6 D 7 CNECK VALVE 3.000 2 C
cv C
42 0
42 "C" MAIN STEAM NEADER SUPPLY CNECK WALVE "
TURBINE DRIVEN AUKILIARY FEEDWATER PL8EP y
2-Ms NRV 201A 11548-CsM 064A 1 0F 6 E.4 M0 STOP CNECK 30.000 NC C
CV C
32 l02 w
x "A" MAIN STEAM NEADER NON-RETURN VALVE r
M 2-Ms NRV 201B 11548-cam-064A 2 0F 6 D-3 MD STOP CNECK 30.000 NC C
CV C
32 lO2 w
m "B" MAIN STEAM NEADER NON RETURN VALVE W
2-Ms NRV 201C 11548-cam 064A 3 of 6 D 3 M0 STOP CNECK 30.000 NC C
CV C
32 lUD w
K "C" MAIN STEAM NEADER NON RETURN VALVE 2-MS PCV-202A 11548-cam-064A 4 0F 6 C 4 A0 GATE 3.000 2 B
EV C
0 FS C
ST C
0 VP OC MAIN STEAM SUPPLY TRIP VALVE TO TURBINE DRIVEN AUXILIART FEEDWATER PlatP e
VIRGICIA POER CDePANY PAGE:
35 0F 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 08/04/94 INSERVICE TESTING PROGRAM. VALVE TABLE NC ISO REL Cs 'RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASBE IW VALVE TEST TEST REO JUST JUST TEST NtmBER NLatRER NUMBER COOR TYPE SIZE class CAT TYPE TYPE POS Y-Csv. Rav-VCu-2 Ms TV-201B 11548 Cam-064A 2 0F 6 C.4 AO CHECK VALVE 30.000 2 B
EV C
1
)
ST C
1 i
VP OC "g" MAIN ETEAM NEADER TRIP VALVE 2 Ms-TV 201C 11548 CSM-0MA 3 0F 6 C.4 A0 CNECK VALVE 30.000 2 8
EV C
1 ST C
1 VP OC "C" MAIN ETEAM NEADER TRIP VALVE e4 2-MS TV-209 11548-CSM 064A 4 0F 6 F-5 A0 GATE 3.000 NC B
EV C
Q' FS C
g ST C
VP OC MAIN STEAM NIGH PRESSURE DRAIN ISOLATION TO CONDENSER y
2 Ms TV 210 11548-CsM 064A 40F6F7 A0 GATE 2.000 NC B
EV C
Q FE C
Q ST C
VP OC MAIN STEAM NIGN PRESSURE DRAIN ISOLATION 70 STEAM GENERATOR BLOWOWN SYSTEM I
0 e
i
I VIRGINIA POWER COMPANY PAGE:
47 0F 66 SURRT UNIT 2 REVIt!ON: 00 THIRD INSERVICE TE5ilWG INTERVAL DATE: 08/04/94
!NSERVICE TESTING PROGRAM. VALVE TA8LE NC ISO REL C5 RR ALT VALVE DRAWING
$NEET DRWG VALVE VALVE AssE IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NLMBER NL8eER C00R TYPE
$1ZE CLASS CAT TYPE TYPE POS V-CSV-RRV-VCh-2 51 025 11548-CDM-089A 10F3E5 CNEM VALVE 8.000 2 AC CV C
5 y
0 LT C
52 I '2 a
RWST SUPPLY CECK VALVE TO CNARGING PLMP SUCTION HEADER 2-51 032 11548-CsM-0898 1 0F 4 E 3 MAN GLOBE 1.000 2 AE CIV LT C
ACl2MULATOR MAKEUP LINE, GUTSIDE CONTAINMENT ISOLATION VALVE 2.s!-046A 1154E CSM-089A 1 0F 3 A 3 CNECK VALVE 12.000 2 C
CV O
2 RWST SUPPLY CNECK VALVE To "A" LOW NEAD SI PUMP SUCTION 2-51 046s 11548 cam 089A 10F353 CEM VALVE 12.000 2 C
cv 0
2 RWST SUPPLY CNECK VALVE TO "B" LOW NEAD $1 PLMP SUITION 2-51 047 11548 cam-089A 1 0F 3 B 5 CNECK VALVE 12.000 2 C
CV O
20 "B" LOW NEAD SI PLMP SUCTION CECK VALVE FROM CONTAINENT SLMP 2-51 050 11548 cam-089A 1 0F 3 C 4 CECK VALVE 10.000 2 C
CV C
2 0
2 "B" LOW NEAD St Pupp DISCNARGE C E CK VALVE 2-51-053 11548-CsM 089A 2 0F 3 B-4 CNECK VALVE 2.000 2 C
CV O
"3" LOW NEAD St PUMP N!NIRM FLOW / TEST LINE DISCHARGE CHECK VALVE 2-s1 056 11548 cam 089A 1 OF 3 8-7 CECK VALVE 12.000 2 C
CV 0
20 "A" LOW NEAD $1 PLMP SUCTION CHECK VALVE FROM CONTAIMMENT SUMP 2 s1-061 11548 cam-089A 2 0F 3 B-5 CHECK VALVE 2.000 2 C
cv 0
"A" LOW EAD 51 PUMP MlWIMUM FLOW / TEST LINE DISCHARE CNECK VALVE 2-51 073 11548-cam 089A 2 0F 3 E 7 MAN GLOSE
.750 2 AE CIV LT C
ACCUMULATOR TEST LINE, OLnSIDE CONTAINMENT ISOLAfl0N VALVE 2-51-079 11548-CBN-0895 4 0F 4 F-7 CNECK VALVE 6.000 1 AC PIV CV C
4 0
4 LT C
RCS COLD LEG St ADMI55!0N CHECK VALVE i
2 51 082 11548-CsM 0898 4 0F 4 E 7 CNECK VALVE 6.000 1 AC viv CV C
4 1
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i VIRGINIA POWER COMPANY PACE:
48 0F 66 5URRY Lai!T 2 REVISION: 00 TMIRD INSERVICE TESTING INTERVAL DATE: 08/04/94 INSERVICE TESTING PROGRAM. VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASE IW VALVE TEST. TEST REG JUST JUST TEST NUMBER NLetBER NLal8ER Coat TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-RRV-VCN-2 51 082 11548 COM 0895 4 0F 4 E-7 CEM VALVE 6.000 1 AC PlV CV 0
4 LT C
RCS COLD LEG SI ADMISSION CE 2 VALVE 2-51 085 11548 cam-089s 4 OF 4 D 7 CNECK VALVE 6.000 1 AC PIV CV C
4 0
4 LT C
RCS COLD LEG $1 ADMISSION C E M VALVE 2-51 088 11548-Cap-089s 4 0F 4 D 7 CNECK VALVE 6.000 1 C
CV C
27 4
0 4
1 RCS NOT LEC 51 ADMIS$10N CNECK VALVE i
2-51-091 11548-CBM-0895 4 0F 4 C-7 CNE N VALVE 6.000 1 C
CV C
27 4
O 4
RCS NOT LEG St ADMISSION C E CK VALVE 2 51*094 11548-Cam-0895 4 0F 4 5-7 CNECK VALVE 6.000 1 C
CV C
27 4
0 4
RCS NOT LEG SI ADMISSION CNECK VALVE W
2-51 107 11548-Cam 0898 10F 4 3 7 CNECK VALVE 12'.000 1 C
CV C
26
'R 0
m y
"A" ACCUMULATOR DISCHARGE CNECK VALVE W4 2 51-109 11548-CDM 0898 1 0F 4 B 8 CHECK VALVE 12.000 1 C
CV C
26 0
M 3
2
- )
"A" ACCUMULATOR COLD LEG ADMISSION CHECK VALVE M
2 51 128 11548-cam-0698 2 or 4 s 6 CNECK VALVE 12.000 1 C
CV C
26 4q 0
N 3
g
- B" ACC1MJLATOR DISCNARGE CHECK VALVE 4
2-51 130 11548-cam 0890 2 0F 4 B 7 CHECK VALVE 12.000 1 C
CV C
26 0
26 3
g "B" ACCUMULATOR COLD LEG ADMIS$10N CNECK VALVE
,4 2 51 145 11548 CeM-089s 3 0F 4 B 5 CNECK VALVE 12.000 1 C
CV C
26 0
a 3
4 o
"C" ACC1MJLATOR DISCHARGE CHECK VALVE h
VIRGINIA poler COMPANY C' ACE:
69 0F 66
$URRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 08/04/94 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER MUMBER NUMBER C00R TYPE SIZE CLASS CAT TYPE TYPE Pos V-CSV-RRV-VCN-y 3
2 SI.147 11548-CSM-0898 3 0F 4 5-7 CNE M VALVE 12.000 1 C
CV C
26 0
26 3
Q
- C" ACOMJLATOR COLD LEG ADNISSION CNECK VALVE 2 51 150 11548-CSM 06?A 3 0F 3 F-6 MAN GLOSE
.750 2 AE CIV LT C
BORON INJECTION TANK BYPASS LINE ISOLATION VALVE. TO RCS COLD LEG 2 51-174 11548-CBM 089A 3 0F 3 D 6 MAN GLOBE
.750 2 AE CIV LT C
HIGN NEAD SAFETY INJECTION TO RCS 2-51 224 11548 cam 0895 40F4F3 CNECK VALVE 3.000 2 C
CV o
4 HIGN NEAD SI FROM CNARGING PUMPS TO RCS COLD LEGS, INSIDE CONT CNE M VALVE 2 51-225 11548 CAM 0898 4 0F 4 E.3 CNE M VALVE 3.000 2 C
CV 0
4 NIGH NEAD SI FR(BI CHARGING PL8FS 70 RCS COLD LEGS, INSIDE CONT CNE M VALVE 2-SI 226 11548 cam-0898 4 0F 4 C 3 CNECK VALVE 3.000 2 C
CV o
4 HIGN NEAD St FROM CHARGING PUMPS TO RCS NOT LEGS, INSIDE CONT CMECK VALVE 2-SI 227 11548-CBM-0898 4 or 4 C-3 CHECK VALVE 3.000 2 C
CV 0
4 NIGH NEAD SI FROM CHARGING PLpr5 TO RCS NOT LEGS, INSIDE CONT CNECK VALVE 2-51 228 11548 CsM-0896 4 0F 4 B 3 CNECK VALVE 6.000 2 C
CV 0
4 LOW NEAD SI FROM LNSI Ptsr 70 RCS NOT LEGS, INSIDE CONT CNECK VALVE 2 51-229 11548-cam 0898 4 OF 4 B 3 CNECK VALVE 6.000 2 C
CV 0
4 LOW NEAD SI FROM LMSI PLDP TO RCS NOT LEGS, INSIDE CONT CHECK VALVE 2 SI 235 11548 CsM 0898 4 0F 4 F-7 CHECK VALVE 2.000 1 C
CV C
4 0
4 i
l NIGH NEAD SI TO RCS COLD LEG, INSIDE MISSILE
(
BARRIER CHECK VALVE
\\
2 SI-236 11548-CBM-0898 4 0F 4 E 7 CHECK VALVE 2.000 1 C
CV C
4 0
4 MIGN HEAD SI 70 RCS COLD LEG, INSIDE MISSILE l
BARRIER CNECK VALVE l
2-51 237 11548 CBN-089B 4 0F 4 D-7 CNECK VALVE 2.000 1 C
CV C
4 l
0 4
l l
l
VIRGINIA PQhER COMPANT PAGE:
53 CF 66
$URRT UNIT 2 REVISION: 00 TN!RD INSERVICE TESTING INTERVAL DATE: 08/04/94 INSERVICE TESTING PROGRAM - VALVE TABLE NC 180 REL CS RR ALT VALVE DRAWING SMEET DRWG VALVE VALVE ASIE IW VALVE TEST TEST REC JUST JUST TEST NL8GER Ni.mgER IDIBER C00R TYPE SIZE CLASS CAT TYPE TYPE Pos V-CSV-RRV VCN-2 SI MOV-2867D 11548 CBM-089A 3 0F 3 E 6 No GATE 3.000 2 A CIV EV C
18 0
18 LT C
ST C
18 0
18 VP GC BORON INJECT!0N TANC QUTLET TO RCS COLD LEG, CUTSIDE CONTAINMENT ISOLATION VALVE 2 31-MOV 2869A 115L8 cam 089A 3 0F 3 C-7 no GATE 3.000 2 A CIV EV C
25 0
25 LT C
ST C
25 0
25 VP OC NIGN NEAD $1 FROM CMARGING NEADER TO RCS NOT LEGS, GUTSIDE CONTAINMENT ISOLAT10N VALVE 241-MOV 2869s 11548 CeM-009A 3 0F 3 E.4 No GATE 3.000 2 A CIV EV C
25 0
25 LT C
ST C
25 0
25 VP GC HIGN HEAD $! FROM CHARGING NEADER TO RCS IIOT LEGS, OUTSIDE CONTAllNIENT ISOLATION VALVE 2 SI-MOV-2885A 11548-cam-089A 2 0F 3 5-5 M0 GATE 2.000 2 A
EV C
LT C
$2 g
ST C
y YP OC "A" LOW NEAD S1 PlatP MINIMUM FLOWTEST LINE ISOLATION 2 SI MOV-2885B 11548-CSM 089A 2 0F 3 8 4 M0 GATE 2.000 2 A
EV C
i i
LT C
S2 2
ST C
Q
)
VP GC
- B* L0bi NEAD $1 PtaqP MINIDRJM FLOW / TEST LINE ISOLATION 2-SI-MOV-2885C 11548-Cam-089A 2 0F 3 S-4 M0 GATE 2.000 2 A
EV C
7 lq LT C
52 t
ST C
y l
VP OC
- B" LOW NEAD St Pta4P MINIMUM FLOWTEST LINE ISOLAfl0W
=a 2-SI-MOV 28850 11548-CSM 089A 2 of 3 B-5 M0 GATE 2.000 2 A
EV C
lD2 LT C
52 ST C
I 1
I
VIRGINIA POWER COMPANY DAGE:
59 0F 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 08/04/94 INSERvlCE TESTING PROGRAM. VALVE TABLE NC 130 REL CS RR ALT VALVE DRAWING SNEET DRWG VALVE VALVE A$ BEE IW VALVE TEST TEST REQ JUST JUST TEST NUMSER NLMBER 1484KR COOR TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-RRV VCm-2 SW 108 11548 CsM-071B 1 0F 2 5 4 CNEM VALVE 2.000 3 C
CV C
0 50 CNARGING PUMP SERVICE WATER PLDP CHEM VALVE 2-SW-113 11548-CeM-0718 1 0F 2 s-7 CNE N VALVE 2.000 3 C
CV C
0 50 CHARGING PLBIP SERVICE WATER PtaqP CKK VALVE 2 SW-206 11548-CBM-071A 3 0F 3 E-8 MAN GATE 2.000 2 AE CIV LT C
CONTAINMENT ISOLAfl0N VALVE FOR SERVICE WATER DRAINS 70 NEAT EXCHANGER 2 SW-203 11548. cam-071A 3 0F 3 E 8 MAN GATE 2.000 2 AE CIV LT C
CONTAltNIENT ISOLAfl0N VALVE FOR SERVICE WATER DRAINS 70 NEAT EXCNAN K R 2-SW-246 11548 CBM-071A 3 0F 3 D 8 CNEM VALVE 3.000 WC C
CV 0
RECIRCULATION SPRAY NEAT EXCNANGER SERVICE WATER RETURN VENT VALVE 2 SW-247 11548 CBM-071A 3 0F 3 D.7 CNE M VALVE 3.000 3 C
CV O
46 RECIRCULAfl0N SPRAY NEAT EXCNANGER SERVICE WATER SUPPLY VENT VALVE r
2 SW-248 11548-CBM-071A 3 0F 3 D 7 CNE M VALVE 3.000 NC C
CV 0
REclRCULATION SPRAY K AT EXCNANGER SERVICE WATER RETURN VENT VALVE 2-SW-249 11548-CBM-071A 3 0F 3 0-6 CNEM VALVE 3.000 3 C
CV 0
46 RECIRCULATION SPRAY KAT EXCNANGER SERVICE WATER SUPPLY VENT VALVE 2 SW-250 11548-CSM-071A 3 0F 3 D*6 CNE M VALVE 3.000 NC C
CV 0
RECIRCULATION SPRAY NEAT EXCHANGER SERVICE WATER RETURN VENT VALVE 2-SW-251 11548-CBM-071A 3 of 3 D 6 CNEK VALVE 3.000 3 C
CV O
46 RECIRCULATION SPRAY KAT EXCNANGER SERVICE WATER SUPPLY VENT VALVE 2 SW-252 11548-cam 071A 3 0F 3 D-5 CNE K VALVE 3.000 NC C
CV O
RECIRCULAfl0N SPRAY MEAT EXCNANGER SERVICE WATER RETURN VENT VALVE 2 SW-253 11548-CSM 071A 3 0F 3 D-5 CHE N VALVE 3.000 3 C
CV 0
46 l
I
VIRGI))A P0bER CCMPANY PAGE:
60 0F 66 SURRY UNIT 2 REVISION: 00 I
-TNIRD INSERVICE TESTING INTERVAL DATE: 08/G4/%
INSERVI E TESTING PROGRAM - VALVE TABLE NC 180 REL CS RR ALT l
VALVE DRAWING
$NEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST JUST TEST NLMBER NUMBER MUMBER C00R TYPE SIZE CLASS CAT TYPE TYPE POS V-CSV-RRV-VCN-1 1
1 RECIRCULATION SPRAY NEAT EXCNANGER SERVIE WTER SUPPLY VENT VALVE i
1 2 SW-442 11548-cam-071B 10F2B4 CNECK WALVE 2.000 3 C
CV O
50 CNARGING MMP SERVICE ETER PUNP OISCNARGE CNECK VALVE 2 SW445 11548-cam-0715 1 0F 2 B-6 CNECK VALVE 2.000 3 C
CV 0
50 CMARGING PUMP SERVI M M TER PUMP OISCNARGE CNECK VALVE 2 SW-MOV 201A 11548 cam-071A 3 0F 3 B.4 NO BFLY 36.000 3 B
EV C
ST C
VP OC SEARING COOLING M TER NEAT EXCNANGER ISOLATION VALVE 2-SW-MOV 201B 11548 CSM-071A 3 0F 3 B.4 NO BFLY 36.000 3 5
EV C
3 ST C
VP OC REARING COOLING W TER MEAT EXCNANGER ISOLATION VALVE 1
2 $W-MOV 202A 11548 cam 071A 2 0F 3 D-6 MO BFLY 42.000 3 8
EV C
ST C
i WP OC SERVICE E TER NEADER RUPPLY ISOLATION TO COMPONENT COOLING NEAT EXCMANGERS 2 SW-MOV 2028 11548 CcM 071A 2 0F 3 D-5 MO BFLY 42.000 3 B
EV C
ST C
VP OC SERVICE ETER NEADER SUPPLY IBOLATION TO COMPONENT COOLING NEAT EXCMANGERS 2 SW-MOV-203A 11548 CBM-071A 3 0F 3 B 8 M0 BFLY 30.000 3 8
EV 0
ST 0
W K
SERVICE WTER NEADER SUPPLY ISOLATION TO RECIRC SPAAY MEAT EXCHANGERS 2-SW-MOV-2038 11548 CBM 071A 3 0F 3 5 8 No BFLY 30.000 3 5
EV' O
ST 0
W K
SERVICE W TER NEADER SUPPLY 180LATION 70 RECIRC SPRAY NEAT EXCNANGERS 2 SW-MOV-203C 11548 cam 071A 3 0F 3 B-3 M0 BFLY 30.000 3 8
EV 0
ST 0
VP OC I
i 1
J VIRGINIA POWER COIGPANY PAGE:
61 CF 66 SURRY UNIT 2 REVIS10N: 00 THIRD INSERvlCE TESTING INTERVAL DATE: 08/04/94 INSERVICE TESTING PROGRAM. VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SNEET ORWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST Jusi TEST NUMBER NUMBER 3RatBER C00R TYPE SIZE CLASS CAT TYPE TYPE P0s V-CsV-RRY. VCN.
SERV!CE WATER NEADER SUPPLY ISOLAfl0N TO RECIRC SPRAY MEAT EXCHANGERS 2-SW-Mov-203D 11548-Cam-071A 3 OF 3 8-2 800 BFLY 30.000 3 5
EV O
ST 0
VP OC SERVICE WATER HEADER SUPPLY ISOLATION 70 RECIRC SPRAY MEAT EXCMANGERS 2-SW-le0V-204A 11548-cam-071A 3 of 3 0 7 No BFLY 24.000 3 8
EV C
0 ST C
0 VP OC SERVICE WATER SUPPLY To "A" RECIRC SPRAY MEAT EXCMANGElt, CUTSIDE CONT ISOLAfl0N VALVE 2-SW-MOV-2048 11548-cam-071A 3 0F 3 D-6 140 BFLY 24.000 3 5
EV C
0 ST C
D VP OC SERVICE WATER SUPPLY 70 "B" RECIRC SPRAY NEAT EXCHANGER, WTSIDE CONT ISOLATIDW VALVE 2 SW-MOV-204C 11548-cam-071A 3 OF 3 D-5 800 BFLY 24.000 3 8
EV C
0 ST C
0 VP OC SERVICE WATER SUPPLY TO *C" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2-SW-MOV-2040 11548-CBM-071A 3 0F 3 D 4 800 BFLv 24.000 3 8
EV C
0 ST C
0 VP OC SERVICE WATER SUPPLY 70 "D" RECIRC SPRAY MEAT EXCMANGER, QUTEIDE CONT ISOLATION VALVE 2 SW-Mov 205A 11548-cam 071A 3 0F 3 D 8 180 BFLY 24.000 3 5
EV C
0 ST C
0 YP OC SERVICE WATER RETURN FROM "A" RECIRC SPRAY HEAT EXCMANGER, CUTSIDE CONT ISOLATION VALVE 2 SW Mov-2058 11548-CBM-071A 3 0F 3 D 7 M0 BFLY 24.000 3 B
EV C
0 ST C
0 VP OC
e VIRGINIA POLER COMPANY PAGE:
62 CF 66 SURRY UNIT 2 REVIS!DN: 00 THIRD INSERVICE TESTING INTERVAL DATE: 08/04/94 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING
$NEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NLMBER NLMBER C00R TYPE SIZE CLASS CAT TYPE TYPE Pos V.
CsV. RRV VCN-SERVIE WTER RETURN FROM "B" RECIRC SPRAY NLM EXCHANGER, GUTSIDE CONT Is0LATION VALVE 2 BW-MOV 2tSC 11548 car-071A 3 0F 3 D-6 M0 BFLY 24.000 3 s
EV C
0 ST C
0 VP OC SERVIE WATER RETURN FR(M "C" REclRC SPRAY MEAT EXCNANGER, GUTSIDE CONT Is0LATION VALVE 2 SW-Mov 2050 11548 CsM-071A 3 0F 3 D-5 No BFLT 24.000 3 8
EV C-0 ST C
D VP OC ORVIE WATER RETURN FROM "D* RECIRC SPRAY AEAT EXCHANGER, CUTSIDE CONT ISOLATION VALVE 2 SW TCV-208A 11548 CaN-071B 1 0F 2 E-7 A0 GATE 1.500 3 5
EV 0
FS O
ST 0
47 SERVI E WATER TO CHARGING PUpr LUBE O!L COOLER TEMPERATLEtE CONTROL VALVE 2 SW-TCV-208e 11548 CaN 0715 1 0F 2 E 5 A0 GATE 1.500 3 8
EV 0
FS O
ST 0
47 SERVIE WATER TO CNARCING PLMP LUBE CIL COOLER TEMPERATURE CONTROL VALVE 2 SW-TCV 208C 11548 CBM 0715 1 0F 2 E-4 A0 GATE 1.500 3 8
EV 0
FS 0
ST 0
47 SERVIE WATER TO CHARGINC PUMP LUBE OIL COOLER TEMPERATURE CONTROL VALVE 1
i t
l a
1 1
RELIEF REQUEST V-26 System Safety Injection Valve (s):
2-SI-107 2-SI-109 2-SI-128 2-SI-130 2-SI-145 2-SI-147 i
Category:
C Class 1
Function:
Accumulator Discharge Check OM Part 10 Code Requirements For Which Relief Is Recuested OM Part 10, Section 4.3.2.4 (a) - This section states in part that, "The necessary valve obturator movement shall be demonstrated by exercising the valve and observing that either the obturator travels to the seat on cessation or reversal of flow,,or opens to the as specified in para. position required to fulfill its function, 1.1, or both.
Observation may be by observing a direct indicator such as a position indicating device, or by other indicator (s) such as changes in system l
pressure,' flow rate, level, temperature, seat leakage testing or other positive means."
This section implies that the techniques used to verify obturator movement be applied to every valve on a test frequency that is practical.
Epsis For Reauest 1
Exercise to the Onen Position Non-intrusive techniques are used to verify obturator movement for the SI accumulator discharge check valves.
These techniques i
provide a " positive means" for verifying obturator movement, however, due to the burden of applying these techniques in the field, a sampling program will be used as described in the alternate testing section.
I Exercise to the Closed Position Valves 2-SI-107 and 109, 2-SI-128 and 130, and 2-SI-145 and 147 perform as pairs of valves in series to isolate the accumulators
,A from the reactor coolant system.
The downstream valves, 2-SI-109, 130 and 147 were previously chosen as the isolation valves
]E and were subject to back seat tests while the other valves were 4-15 i
i Revision 0 j
S2PVI3R0 August 4, 1994 i
i 1
RELIEF REQUEST V-26 (Cont.)
~!
considered as backup valves and were not subject to back seat j
tests.
The other set of valves cannot be individually back j
seated with the current piping configuration.
Testing experience has shown that a severe water hammer can be produced by I
attempting to individually test the downstream isolation valve.
{
a To individually test these valves, a reactor coolant system pressure in excess of 1000 psi was needed to properly seat the valves.
The line upstream.was then vented using a 3/4 inch
{
sample line.
Flow in the sample line was monitored to verify j
that the check valve seated.
Also, the accumulator was isolated I
by the upstream motor operated isolation valve.
1 During one test, a steam bubble was created in the volume of pipe upstream of the check valve due to the initial high pressure and temperature in the line, and due to'the subsequent venting of the line and the flashing of water to steam.
When the motor operated isolation valve was opened following the test to restore the accumulator to service, a severe water hammer was created by the collapsing steam bubble.
Although less severe hydraulic H
transients had been observed in previous tests, the potential for system damage became obvious after this test.
Other. test methodologies were evaluated to determine if valve
-j closure could be verified while reducing or eliminating the possibility of creating another water hammer event.
For example, testing at a lower reactor coolant temperature and pressure reduces the amount of water flashing to steam.
However, testing has shown that the check valves do not seat properly at reactor coolant system pressures less then 1000 psi.
It was concluded that with the current system configuration, a test could not be designed that would meet these criteria.
Treating the check valves as a pair of' isolation valves would eliminate the possibility of creating a water hammer event through testing.
The accumulators have level indicators and high/ low tank level alarms in the control room.
Therefore, during normal operation the accumulator level is constantly monitored to ensure that one out of two check valves is seated properly to prevent in leakage from the reactor coolant system.
4-16 l
Revision 0 S2PVI3R0 August 4, 1994
a RELIEF REQUEST'V-26 (Cont.)
3
-Alternate Testina Pronosed Exercise to the Onen Position 9
During the first refueling outage where non-intrusive techniques are used, all valves in the group will be tested to verify that i
the techniques verify valve obturator movement.
During subsequent refueling outages, flow testing will be performed on-i all valves in the group, but the non-intrusive techniques need be applied only to one valve in each group, on a rotating basis, unless indications of problems are identified.
In this case, all valves in the group will be subjected to the non-intrusive techniques.
The test frequency is in accordance with Generic Letter 89-04, Position 2.
Valves 2-SI-130 and 147 are in one group and valves 2-SI-107, i
109, 128 and 145 are in the other group.
Because 2-SI-130 and 147 are downstream from where RHR connects to the SI line, they experience different service conditions than the other valves.
The justification for testing these valves during reactor refuelings was moved to Reactor Refueling Justification RRV-3 Exercise to the Closed Position Valves 2-SI-107 and 109, 2-SI-128 and 130, and 2-SI-145 and 147 perform as pairs of valves in series to isolate the accumulators
?
from the reactor coolant system.
Monitoring the accumulator t
level during normal operation will be'an adequate demonstration t
,3 that one out of two valves in series is seating properly.
If a
leakage past both valves in series to the' accumulators becomes fj unacceptable for normal operation, both valves'will be declared inoperable.
The check valves will not be individually tested to the closed position.
I l
)
4-16a Revision 0 l
S2PVI3R0 August 4, 1994 l
i
j i
RELIEF REQUEST V-50
[
System Service Water i
hl Valve (s):
2-SW-108 2-SW-442 2-SW-113-2-SW-445 y
Category:
C l
Class 3 (2-SW-108,113,'4 4 2,4 4 5 )
Function:
Charging Pump Service Water Pump discharge Check k
Valves OM Part 10 Code Requirements-For Which Relief Is Reauested e
OM Part 10, Paragraph 4.3.2.4(c) reads in part that, " disassembly every refueling outage to verify operability of check valves may be used."
This sentence implies that each valve in the group given above must be disassembled every refueling outage.
i Basis'For Resuest The design basis for the charging pump service water system is currently undergoing reevaluation.
A full flow acceptance criteria will not be avaliable until this reevaluation is complete.
t These check valves can be disassembled while the plant is operating.
To allow for flexibility in planning for refueling outages and still meet the intent of OM Part 10, the valves will
.i be disassembled on a reactor refueling frequency'but not necessarily during refueling outages.
Alternate Testina Prooosed These valves will be placed into two groups and one valve from each group will be disassembled and inspected on a reactor refueling frequency.
A different valve will be disassembled for each inspection.
Valves 2-SW-108 and 113 will be 19 one group, q
(!
and valves 2-SW-442 and 445 will be in the other group.
If a valve fails its inspection, the remaining valves in the group will be disassembled and inspected.
The check valves will be partial stroke tested every three months.
This test frequsncy is in accordance with Generic Letter 89-04,. Position 2.
4-30
~
Revision 0 S2PVI3RD August 4, 1994
l
~
RELIEF REQUEST V-52 System Chemical and Volume Control and i
Safety Injection Valve (s):
2-CH-LCV-2115B 2-SI-MOV-2885A 2-CH-LCV-2115D 2-SI-MOV-2885B 2-SI-25 2-SI-MOV-2885C 2-SI-MOV-2885D i
Category:
A and A/C Class 2
Function:
RWST Isolation Valves OM Part 10 Code Requirements i
For Which Relief Is Reauested OM Part 10, Section 4.2.2.3 (f) - Valves or valve combinations' with leakage rates exceeding the values specified by the owner in (e) above shall be declared inoperable and be either repaired,or replaced.
y Basis For Recuest Q-Q.j i
Valves 2-CH-LCV-2115B and D, and 2-SI-25 are in the supply line to the charging pumps from the RWST.
Valves 2-SI-MOV-2885A, B, C
and D are on test lines that run from the discharge of the low head SI pumps to the RWST. 'During recirculation mode transfer, the~RWST is isolated and the low head SI pumps recirculate highly contaminated water from the containment sump to the reactor
. vessel.
The RWST isolation valves work as a system of valves to protect the RWST from the contaminated sump water.
Permissible valve leakage rates are based on each valve's possible contribution to the total allowable leakage rate to the RWST.
When the leakages from each valve have been measured and summed, an individual valve's permissible leakage rate may have been exceeded but the overall allowable leakage to the RWST may not have been exceeded.
In these cases, a repair or replacement may not be necessary because the system of isolation valves has been verified to be performing adequately.
~
4-32a Revision 0 S2PVI3R0 August 4, 1994
RELIEF REQUEST V-52 (Cont.)
P t
Alternate Testina Pronosed In addition to repair or replacement as corrective actions, an evaluation can be performed which demonstrates that even if a valve has exceeded its permissible leakage rate, the.overall T
leakage rate to the RWST will be maintained below the overall allowable RWST leakage rate.
No repair or replacement is 7
y necessary if the evaluation is performed.
6 l
i 4-32b Revision 0 S2PVI3R0 August 4, 1994
. ~.
4 r
COLD SHUTDOWN JUSTIFICATION CSV-29
. H.
Cold Shutdown Justification Withdrawn h,
-t
'f t
i t
I i
f f
i i
l l
4-60 i
Revision 0 l
S2PVI3R0 August 4, 1994
- COLD SHUTDOWN JUSTIFICATION CSV-32 System Main Steam Valve (s)
- .2-MS-NRV-201A 2-MS-NRV-201B
.j 2-MS-NRV-201C Category:
C y
lN, Class NC l
4 Function:
Main Steam Non-Return Valves Cold Shutdown Justification Valve Descrintion The main steam non-return valves (NRVs) at Surry Power Station are located in the main steam valve house and are a globe type stop check design.
The valves measure approximately 16 feet from the bottom of the valve body to the top of the hand wheel and weigh'almost 18,000 lbs.
The disk is welded to a hollow piston and the whole assembly is free to move about 25 vertical inches-within the_ valve body cylinder..
The disk measures 25.5 inches across and the disk and piston assembly weighs approximately l
l 1,200 lbs.
When:the main steam system is not inservice, a motor L
' operator is used.to run the valve stem down onto the disk to secure the main steam line.
The valves open to allow steam to the turbine.
For accident conditions, the non-return valves-in conjunction with the main steam-trip valves prevent the blowdown of more than one steam
. generator for any break location, even if one valve fails to i
close.
For example, for a break upstream of the trip valve in one line, the closure of either the non-return valve in that line or the trip valves in the other lines prevents the blowdown of the other steam generators.
Method of Testina The piping downstream of each non-return valve leads to a common distribution manifold and cannot be isolated.
Therefore, performing a back seat test using flow is not practical.
- Also, i
valve disassembly and inspection are not practical alternatives i
due'to the size of the valve and the weight of the disk.
4-63 Revision 0 S2PVI3R0 August 4, 1994
1 REACTOR REFUELING JUSTIFICATION RRV-3 I
System Safety Injection i
Valve (s):
2-SI-107 2-SI-109 2-SI-128 2-SI-130 2-SI-145 2-SI-147 l
Category:
C Class 1
1 i
Punction:
Accumulator Discharge Check i
Reactor Refueline Justification These valves cannot be partial or full flow tested during normal operation because the accumulator pressure (600 to 650 psig)'is below Reactor Coolant System pressure and the injection of borated water would upset the reactor coolant chemistry.
During i
cold. shutdown, the RCS pressure still prevents full flow testing.
To ach'ieve full _ flow:through'the valves during reactor refueling, the accumulator would have to be discharged from an initial
_ pressure of 600 psig.
Discharging the accumulator from this pressure would stress the piping system and inject nitrogen into i
the RCS.
Nitrogen in the RCS has been linked-to gas binding of the RHR pumps.
However, the accumuir.tcr can be discharged from a lower pressure _during reactor refuelings when the RCS is depressurized.
At this pressure, full flow conditions'will not be established; however, enough flow will be developed to open the check valves to the full open position.
This event can be verified and documented using non-intrusive diagnostic techniques.
I l
A partial flow test is not practical during cold shutdowns.
The flow from the accumulator is dependent on the pressure differential between the accumulator and the-RCS.
The pressure differential cannot be controlled to the fine degree necessary to H
preclude dumping too much water into the pressuriyar,-thus making d
it difficult to control pressurizar level while pressure is being (a
reduced during cooldown.
Also, dumping cold accumulator water into the RCS could thermally shock the system.
Testina Frecuency Non-intrusive diagnostic techniques will be used to determine that the check valves open to the full open position.
A sampling program will be applied to the non-intrusive techniques as
{
described in Relief Request V-26.
R i
4-71 Revision 0 S2PVI3R0 August 4, 1994 i
b
(
'+
=
REACTOR REFUELING' JUSTIFICATION RRV-5 i
. System. :
RWST Cross Tie-Valve (s):- 2-SI-25 2-SI-400 i
Category:
C-Class 2
Function:. Charging. Pump Suction from RWST Cross Tie Reactor Refuelina Justification Exercising these1 valves during power operation would require the charging pump suctions to be aligned with the refueling water storage tank.
This would cause a' sudden increase in reactor coolant boron inventory.
Full flow for-the charging system can only be established during reactor refueling when the RCS is depressurized.
1 Valve'2-SI-25 must close to preserve inventory from-the Unit'l l
RWST when the cross tie lines are opened.
This: valve is also i
subject to leak testing, which is. performed every reactor
,,4 '
refueling.
Verification of closure will be performed during the i
leak test every reactor refueling instead of every cold shutdown
- g -
because the small increase in safety gained by testing'during c
~
cold shutdown does not justify performing a leak rate test.
.)
i Testina Frecuency These valves will partial flow tested during every cold shutdown and full flow tested ~during every reactor refueling.
Valve.2-S1-25 will be exercised to the closed' position every T'
refueling outage.
g I
I l
1 4-77 Revision 0
,2PVI3R0 August 4, 1994
.