ML20248G366
| ML20248G366 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 10/03/1989 |
| From: | Murphy W VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BVY-89-90, GL-89-04, GL-89-4, NUDOCS 8910100214 | |
| Download: ML20248G366 (142) | |
Text
-
q
)
)
TVERhiONT YANKEE NUCLEAR POWER CORPORATION P. O. BOX 157 GOVERNOR HUNT ROAD VERNON, VERMONT 05354 October 3,1989 BVY 89-90
~U.S. Nuclear Regulatory Commission Washington,;0.C. 20555 Attn: Document Control Desk h
References:
a)- License No. DPR-28 (Docket No. 50-271) b). Code of Federal Regulations, Title 10 Chapter 1, Part-50, Section-50.55a(g) c)
ASE Section XI,1980 Edition through the Winter 1980 Addenda d)- Letter,"Mr. V. L. Rooney, USNRC, to Mr. R. W. Capstick, WNPC,. Subjects. Request for Additional Information - IST l
Program," Docket 50-271, NVY 87-01, dated January 5,1987 e)
Letter, Mr. V. L. Rooney, USNRC, to IH. R. W.' Capstick, WNPC, " Subjects Meeting Summary," Docket 50-271,.NVY 88-074, i
dated May 9, 1988 l
f)
Letter, Mr. W. P. Murphy, WNPC, to Document Control Desk, i
USNRC, " Subject Inservice Testing Program, Revision 9,"
Docket 50-271, FVY 88-63, dated July 28,.1988' g)
Letter Mr. S. A. Varga, USNRC, to All Holders of Light Water Reactor Operating Licenses and Construction Permits,
" Subject Guidance on Developing Acceptable Inservice Testing Programs (Generic Letter No. 89-04)", NVY. 89-75, dated April 3,.'1989.
h)
Letter, Mr. W. P. Murphy, WNPC to Document Control Desk, USNRC, " Subject, ~ Supplemental Response to Inspection Report No. 50-271/86-25, Notice of Violation", dated March 25, 1988.
Subject:
Response to USNRC Generic Letter 89-04: Guidance on Developing l
Acceptable Inservice Testing Programs Dear Sira ll By letter, dated April 3,1989 [ Reference (g)3, USNRC provided clarifying positions to be dsed in developing Inservice Testing (IST) Programs for ASE Code Class 1,2, and 3 pumps and valves. This information has been applied to the Vermont Yankee IST program to assure its adequacy for detecting equipment l
degradation and assuring the operational readiness of this equipment in accor-dance with ASE Section XI.
~
0 ea u%.
P L
i'
1 l
l Page 2 l-It should be noted that the program review performed per Reference (g) follows extensive program review ang revision baspd on the USNRC request for additional IST program information LRefegence (d)J.
Tpisrequestwasthen
)
I followed by a meeting at USNRC Region I LReference (e)J and a subsequent program revision submitted via Reference (f). Many of the issues addressed in Generic Letter 89-04 parallel the issues that were discussed and resolved per the above.
Since Vermont Yankee has not received a Safety Evaluation Report (SER) on its IST program, the subject Generic Letter requires review of the current program and implementing procedures to assure compliance with the stated staff positions. The results of this review are included in Attachment 1.
Changes to the IST program (which resulted from this review and were incorporated via program revision 10) are included in Attachment 2.
A copy of the entire Vermont Yankee Inservice Testing Program, Revision 10, is contained in
! for your information.
We trust that the information contained in this letter is satisfactory, however, should you have any questions or require additional information, please contact us.
Very truly yours, Vermont Yankee Nuclear Power Corporation gWarrenP. Murphy Vice President and Manager of Operations Attachments JCK/mes GL8904.1/IST CC: USNRC Regi.onal Administrator, Region I USNRC Resident Inspector, VYNPC 1
_____________________________J
r 1
i I
s ATTACH:4ENT 1
1.
Full Flow Testina of Check Valves Vermont Yankee performed extensive IST Program review per References (d) and l
(e) to identify all check valves that have a safety function in the open I
direction and to ensure adequate testing of the open function.
In response to clarifying positions presented in this Generic Letter, this review was repeated to confirm that all valves with an open function were identified.
Current test methods for.the valves in this group were then individually reviewed to determine Generic Letter compliance.
Based on the above review, Vermont Yankee has reconfirmed that all of these check valves are either full-flow tested as described in Generic Letter item
- 1 or are verified to open using the alternate methods of disassembly described in Generic Letter item #2.
Therefore, it is concluded that current practices are in full compliance with items 1 and 2 of this Generic Letter.
2.
Alternative to Full Flow Testino of Check Valves See the response to Item #1 above.
3.
Back Flow Testing of Check Valves Vermont Yankee performed extensive IST Program review per References (d) and (e) to identify all check valves that have a safety function in the closed direction and to ensure adequate closure testing of these valves.
In response to the positions presented in this Generic Letter, this review was repeated. Vermont Yankee reconfirmed that current test practices conform to the guidelines presented in the Generic Letter with the following two exceptions.
Two check valves, which are located in series in the Gland Seal Condensate Pump discharge line on the Reactor Core Isolation Cooling Pump skid, have in the past been tested as a pair. Since they are installed in series, this test does not assure closure of both valves. Therefore, Relief Request Basis V30 has been added to the program to assure the closure function of each valve separately. The current IST program listing for these valves has been revised accordingly.
The above progtam revision and corresponding procedure change, which will be incorporated prior to the current operating cycle test, complete full compliance with this item.
l
- 4. Pressure Isolation Valves (Low Pressure /High Pressure Interface) a.
The Vermont Yankee response to Generic Letter 87-06, " Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves",
identified 14 valves as Pressure Isolation Valves (PIV's).
(NOTE:
PIV's are defined as two normally closed valves in series that isolate the reactor coolant system from an attached low pressure system.) Of these 14, the following 6 PIV's are listed in Plant Tech. Specs. as 1
Primary Containment Isolation Valves with specified testing:
)
4
~
V10-18 RHR Shutdown Cooling Isolation (Inboard)
V10-17 RHR Shutdown Cooling Isolation (Outboard)
V2-74 Main Steain Line Drain (Inboard)
V2-77 Main Steam Line Drain (Outboard)
V2-39 Recirculating Loop Sample (Inboard)
V2-40 Recirculating Loop Sample (Outboard)
All of the above valves.are listed in the IST Program as Category A or A/C Valves and are tested per Tech. Spec. requirements.
(NOTE: Although not required by this Generic Letter or Vermont Yankee Tech. Specs., the remaining 8 valves identified in response to Generic Letter 87-06 referenced above, are also listed in the IST Program as Category A or A/C Valves.)
In summary, current practices are in full compliance with item da of this Generic Letter.
b.
Per letter; Vermont Yankee to USNRC, " LWR Primary Coolant System Pressure Isolation Valves, " dated March 14, 1980, it was concluded that the Event V valve configuration does not exist at Vermont Yankee.
(NOTE: Event V PIV's are defined as two check valves in series at a low pressure /RCS interface whose failure may result in a LOCA that bypasses containment.) Therefore, the Generic Letter item on Event V PIV's does not apply.
- 5. Limitina Values of Full-Stroke Times for Power Operated Valves Vermont Yankee performed extensive review of past power operated valve stroke time data in 1987 while responding to Reference (d). The results of this review concluded that power operated valve degradation can be more readily identified by using stroke time acceptance criteria from ANSI /ASME Standard OM-10, " Inservice Testing of Valves", Draft 11.
These criteria were then incorporated into Revision 9 of the Vermont Yankee IST Program (Reference [f]).
In addition to the above, all power operated valves having a limiting stroke time identified in Technical Specifications or the plant safety analysis were identified. These limits were also included in Reference (f) and preclude OM-10 standard acceptance when they are more limiting.
Therefore, Vermont Yankee power operated valve testing practices assure that safety analysis assumptions are adequately confirmed.
Based on the above, improvements to power operated valve testing that Vermont Yankee instituted per Reference (f) are in full compliance with stated staff positions. No changes to the IST Program are necessary per this Generic Letter.
- 6. Stroke Time Measurements for Rapid-Actino Valves
)
While performing the power operated valve stroke time review discussed in Item #5 above, Vermont Yankee also reviewed data from rapid-acting valves.
Based on that review, acceptance criteria from ANSI /ASME Standard OM-IO, Draft 11 were also incorporated for rapid-acting valves to further enhance the IST program.
l
\\
l 1
,-c r-d 1
Since the testing criteria presented by the staff in this Generic Letter are the same as those adopted by Vermont Yankee in 1988 per Reference (f), no further IST Program changes are necessary. Current test methods are in full compliance with the Generic Letter, q
l
- 7. Testino Individual Control Rod Scram Valves in Boilina Water Reactors Vermont Yankee reviewed current test methods for the Control Rod Drive system valves identified. Based on this review, the following IST Program changes were made:
a)
The closure function of the cooling water header check valves is tested during normal control rod motion surveillance per Generic Letter guide-lines. However, these valves were not previously included in the IST i
program. They have now been added to the program listing and will con-tinue to be tested in the above manner.
Implementing procedures have been revised accordingly.
b)
Although not a Tech. Spec. requirement, Vermont Yankee performed a pressure decay test during the 1989 refueling outage to verify closure of the charging water header check valves. Subsequent issuance of this Generic Letter then provided clarifying positions for an identical test during each future refueling outage. Therefore, this testing practice will be continued via the appropriate revision to the IST Program valve listing. However, based on 1989 test results, Vermont Yankee has concluded that performance of this test on an alternating refueling outage basis is appropriate. Relief Request Basis V-21, which discusses 1989 testing, has been incorporated into the program to docu-ment this test method and frequency.
Based on existing testing practices and the above identified program rev-sions, Control Rod Drive valve testing is in full compliance with this Generic Letter with the exception of the frequency of the charging water header pressure decay test.
- 8. Startina Point for Time Period in TS Action Statements The method used at Vermont Yankee for determining equipment operability /inoperability and entry into any corresponding Tech. Spec.
Action Statement has been delineated in Reference (h). An excerpt from that letter, describing current practices, is as follows:
After completion of the testing, the results must be assessed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />.
If the Shift Supervisor has good reason to believe the readings may not represent the true condition of the pump, such as transcription error, instrument malfunction, or operator error in using or reading the instrument, he can indicate he has rejected the data and the reason (s) why and retake the data.
If the results from the pump. testing indicated that the pump is in the
" ALERT" range:
m Ops will immediately initiate a Maintenance Request (MR) and for-ward it to Maintenance (further testing of the pump is discretionary).
Maintenance will develop a plan to identify or fix the problem, or justify new reference parameters prior to the next. test (two weeks).
~
Based on:the results of the next test, Maintenance will identify any other actions necessary to correct the problem and remove the
-pump from the." ALERT" range.
Ift the results from the pump testing indicated that.the pump is in the
" Required Action" range:
'The pump shall immediately be declared inoperable.
. Ops will immediately initiate an MR and forward it to Maintenance (further testing of the pump is discretionary).
Maintenance will develop a plan to identify and-fix the problem, or justify new reference parameters.
NOTE: The above methods are also applied to valve testing results.
These test methods, which were reviewed by NRC and accepted via Region I Inspection Report Nos. 50-271/88-06 and 50-271/88-16, are deemed to be in L
full compliance with ASME Section XI.
No further actions / program revisions l
are necessary.
- 9. Pump Testina Usino Minimum-Flow Return Line With or Without Flow Measurina Devices L
All Section XI pump testing performed per the Vermont Yankee IST Program is l
' performed at full flow conditions. Therefore, the concerns' referenced in this Generic Letter on the use of minimum-flow data for pump performance monitoring do not-apply.
In addition, although tested under full flow conditions, Vermont Yankee currently takes relief from portions of IWP-3100 for testing of pumps in the following three systems:
1 a)
Diesel Fuel Oil Transfer (FOT) System b)
Service Water (SW) System c)
Reactor Building Closed Cooling Water (RBCCW) System The basis for relief from these requirements is due to the large number of system variablas that cannot be readily altered to allow for regular repeatable pump testing in these systems. However, pump vibration and L
hydraulic parameters are still recorded and analyzed to the degree possible l
on a quarterly basis.
1
To enhance current testing methods and to assure compliance with this Generic Letter, the following testing revisions and IST program changes have been made for these systems, a)
Diesel Fuel Oil Transfer (FOT) System - Current test methods of recording and analyzing pump differential pressure and vibration will continue as mentioned above.. The practice of ensuring that each pump is capable of supplying fuel oil to the day tanks at a-flow rate greater than that required by the associated diesel generator under full load operation will also be continued on a quarterly basis.
In addition, a full flow test will be performed once per operating cycle.
The full flow test frequency has been documented via a revision to Relief Request Basis - P6 (attached) b)
Service Water (SW) System - Current test methods for calculating flow rate, differential pressure, and total discharge head using available data input will be continued in parallel with measurement of vibration levels. These methods are discussed in Relief Request Basis - Pl.
In addition, portions of the system will be isolated during each refueling outage and all four SW pumps will be subjected to a full flow test using removable flow indications. This additional testing and test frequency has been incorporated via a revision to Relief Request Basis
- P1 (attached).
c)
Reactor Building Closed Cooling Water (RBCCW) System - Current test methods will be continued as described in Relief Request Basis - Pd.
In addition,- flow instrumentation will be incorporated no later than the end of the 1990 refueling outage to allow for full flow measure-ment. Full flow tests will then be conducted on an annual basis as described in the revision to Relief Request Basis - P4.
The above referenced program changes and equipment modifications will then complete full compliance with this issue in the Generic Letter.
Corresponding implementing procedures will be revised prior to performing the above testing.
- 10. Containment Isolation Valve Testina Vermont Yankee individually reviewed each valve defined as a Containment Isolation Valve (CIV) as specified in 10CFR50, Appendix J for inclusion in the IST Program. This review concluded that the following 8 valves are defined as CIV's but are not currently listed as Category A or A/C valves in the IST program:
V3-412A/B Recirculation Pump Seal Purge Check Valves V3-413A/B Recirculation Pump Seal Purge Check Valves V16-19-51 Containment Gas Leak Monitoring System Check Valves V16-19-52 Containment Gas Leak Monitoring System Check Valves V14-11A/B Core Spray Injection Valves The IST program has been revised to include these valves as Category A or l
A/C and they have been added to Relief Request Basis GV-3 which specifies their testing per Appendix J.
(NOTE: Outboard Core Spray Injection Valves l
V14-11A/B would not generally be considered CIV's since there are two nor-mally closed valves downstream of each of them. However, the Appendix J program takes an exemption from testing one of the two downstream valves in each line, thereby making V14-11A/B CIV's.)
I In addition, based on review of Vermont Yankee test data and the NRC staff's l
position that Paragraph IWV-3427 (b) may not be useful for determining valve degradation,. relief from this paragraph is documented in Relief Reqtaest l
Basis GV-3.
l l
11 IST Program Scope Vermont Yankee reviewed the scope of the IST program, including equipment identified by the Generic Letter as being frequently omitted. Results of this review concluded that the chilled water system pump and check valves that supply cooling to the Control Room Ventilation system should be added to the scope of the Vermont Yankee IST Program. This addition and related procedure changes have been completed with revised program pages included in.
(NOTE:-Items 1,2,3 of this Generic Letter concerning check valve testing, and. item 9 concerning pump flow testing, were applied when making this addition to the program.. It is concluded that testing of the I
added equipment complies with the guidelines presented in this Generic j
Letter.)
l Based on the above, the Vermont Yankee IST Program, as revised by this attachment, is deemed adequate in meeting ASME Section XI requirements.
JCK/mes:GL8904.1/IST l
l l
l l
l l
l l
l l
l l'
1 l
l L___--__----_---._-_.--
M'~ -
l 4
4 ATTACHMENT 2 l
l l
l l
S e
e l
K e
l l
b R
l b
b a
A b
a a
T M
a T
T
/,
E T
/
/
1 4
6 R
/,
3, 3,
3, P
P e
, 3, 3,
1 1
1
,l 1
1,
1 2b 3
S 7
P 2, s
s epa s
e P 2,P P 2, e
e
,l T
e l
B1 t
t b8/
t b818 B1 R
o o
aR1 o
aR R1R R s N
N T R N
TRsR Rs e
e e
e e
et e
eet e
eet et et eo ne eeo e
eeoeoeo SN S
S SSN S_
SSNSNSN S
LS PVE LR P
L L
r P
oBUR SLLO E
I T
I R
T VB V
V V
V V
V V
V V
V N
I A
V UQ W
T QO Q
O Q
Q Q
Q S
L E
F T
E C
S I
S P
P P
P P
P P
V PE A
A A
A A
A A
R AR E
P SN I
TS iES i
i i
i i
i i
i PLE P
P P
P P
P P
P NR I P D
E NE N
N PS YTY I C LN I E BU T
T T
T T
T T
T T
T AQ Q
Q Q
Q Q
Q Q
Q Q
Q RE ER PF O
3 2
2 2
2 2
3 3
3 AL SC ECG9 92 292 1
8429 2
7 NN5 5/
76/
7 67/5 6
3 EI 1111 11 1 1
111 1 3 1
2 RW1 1
1 1 1
1 1 1
1 1
EA9 9
99 9
99 9
9 9
FR1 t 1 t 11 t 1
11 t 1 t 1
1 ED - h - h
- - h
- - h - h R
GSGS GGS G
GGSGS G
G M
I S
C O
E W
C C
I F
T S
P C
S D
HB B
RB B
Y DD
/
/
/
/
C S
A AA A
AA A
.A
/
AAW1 1 1 1
1 1W 1
V P
11S -
- - C
- 1H M
- - R0R 4 5C 6
79C 2 -
U 78H1 H 4 4L 4
45B 9PR P
PPRPR PPS P
l-Relief' Request Basis
[
NUMBER:
P1 SYSTEM:
Service Water PUMP:
P7-1A-D CLASS:
3 TEST REQUIREMENT:
Quarterly testing per IWP-3100 BASIS FOR~ REQUEST:
For these pumps, neither. inlet pressure nor flow rate can be directly measured.
Inlet pressure can not be directly measured as these pumps are of the deep well, centrifugal turbine type which rel, on intake structure water level for suction head.
Flow rate :an not be directly. measured due to the absence of sufficient straight piping to allow for instrument installation.
In lieu of direct measurement, flow' rate, differential pressure and total discharge head-are calculated using a computer program which fits a head / capacity' curve from the data inputs of intake structure water level and temperature and pump discha"ge pressure. The results are evaluated against the quantitative values given in Table 1.
Since flow can not be throttled nor differential pressure fixed, (dependent on river water levels and temperatures and system heat loads) the data received from the computer program may not be a true indication of the pump's perfor-r.ance. Vibration levels are also subject to change since the reference para-meter of differential pressure can not always be achieved.
P - 3 Rev. 10 j
L
ALTERNATE TESTING:
E Portions of the Service Water system will be isolated during each refueling g
outage and all four Service Water pumps will be subjected to a full flow test using temporarily installed flow instrumentation. Data from this test will be evaluated against the values given in Table 1 and will be used to calculate a revised head / capacity curve.
This revised curve will then be used in the per-formance evaluation discussed above using quarterly readings, and will be ana-lyzed for trends to the degree possible.
In addition, the current practice of taking one pump out of service during each operating cycle for preventive maintenance overhaul will be continued.
P - 4 Rev. 10 1
- - - - - - - " - - - - - - - - - - - - - - ^ "
w Relief. Request Basis NUMBER:
P4 SYSTEM:
Reactor Building Closed Cooling Water PUMP:
P59-1A/B CLASS:
3 TEST REQUIREMENT -
Inservice test quantities'per IWP-3100, Table IWP-3100-1 BASIS FOR RELIEF:
Table IWP-3100-1 specifies the Inservice Test Quantities to be measured or observed. Differential pressure varies due to the distribution of cooling water to the various loads as regulated by temperature and pressure control valves in the system.
Inlet pressure also cannot be measured before the pump test since the pumps are normally running. The vibration levels are also subject to change since the reference parameters cannot always be achieved.
ALTERNATE TESTING:
Quarterly readings will continue to be taken, recorded, and analyzed for trends to the degree possible.
Due to the variation of cooling water distribution referenced above, flow testing must be performed at a climatic condition producing a reference pump discharge pressure. Therefore, full flow testing will be performed once per year as climatic conditions permit.
(Note: Since pump flow indication is not currently available, it will be incorporated no later than the end of the 1990 refueling outage.)
l l
P-7 Rev. 10
m Relief Request Basis l
I
~ NUMBER:
P6 SYSTEM:
Fuel Oil Transfer PUMP:-
P92-1A/B CLASS:
3
- TEST REQUIREMENTS:
Differential pressure and flow measurements per IWP-3100.
Table IWP-3100-1.
' BASIS FOR RELIEF:
Fuel oil pumps are positive displacement pumps which are in a fixed resistance system. Per Table IWP-3100-1, Note 1, it is required to measure dif-ferential pressure or flow rate.
There is no method available for measuring
- flow. Differential pressure varies with the amount of fuel in the diesel' fuel
- storage tank, TK-40-1A.
The differential pressure is also subject to viscosity changes of the fuel oil due to seasonal temperature variations. These variations are not indicative of positive displacement pump performance.
t ALTERNATIVE TESTING:
Ensure that each pump is capable of supplying fuel oil to the day tanks at a flow rate greater than that required by the associated diesel generator under full load operation. This shall be verified by an increase in day tank level during each surveillance test of full load operation.
In addition, once per operating cycle, day tank level will be reduced to allow for a pump flow test. Day tank level increase will be measured versus pump operating time to calculate a flow rate. This rate will then be trended and analyzed.
P-9 Rev. 10 m
__mm
_m___2-.
1
. Relief Request Basis i
i NUMBER:
SYSTEM:
Contro1' Room Ventilation Cooling PUMP:
SP-1 CLASS:
~3 TEST REQUIREMENTS: 7,nservice test quantities 'per IWP-3100, Table IWP-3100-1 BASIS FOR RELIEF:
Per response to USNRC Generic Letter 69-04, " Guidance On Developing-Acceptable Inservice Testing. Programs," Vermont Yankee committed to adding the Control Room Ventilation system to the IST program.
In addition, since flow indication is not presently available for puup SP-1, it was committed to be incorporated no later than the end of the 1990 refueling outage and tested quar-terly thereafter.
i S
ALTERNATIVE TESTING:
Until flow indicating equipment is ir. stalled, quarterly pressure and vibra-tion readings will be taken, recorded, and analyzed for trends to the degree possible.
l l
P - 10 Rev. 10 I
I
9. :4 Ii il!'
l 0:.
. 1 e
l ba T
8 1
d 2
6 s
n 1
k e a e 1
r l
l 9
e b
3 b
1 s
a V
a e
T G
T G
R d
S d
n A
n a
A a
O 3
5 5
1 6
T N
V 1
1 1
I G
V V
e V
V G
l N
O S
B b
g g
I A
R A
a n n
N R
R R
T a
A AR e e e e e e
O e e e e e e
S - S S
S s
S sev gi t
ia J
J R
t n T
T R
sr L
L ee l t l
A s
t f s T
T 1
V V
ee L
L L
C C
iu q lee RR s
.tnem t e V
T T
S T
T T
sr C QM gN C 4N L
QN ei u t
q' o
ts n
l o ai at C
O C
C C
0 0
C ri os s o I
P rot e O
D O
D ap M
N M
M uy t T c
A ee C
vp K
A A
K L
F A
E l y C
G G
C G
E G
C aT V
)
et n.
ii 8
B S
0 5
1 3
1 S(
/e ev vi is A
A A
A A
A A
A t s ca AP D
rr eo C
m a
u m
vn l e at B
m m
VaC A
m m
m m
m e
g t
o s
t 5
v a
1 S
n 0
i 9
8 8
1 T
w d
1
- 2 1
e r
1 G.
G.
G.
F.
F.
1 1
r o
- 4
- 4 o
o 11 C
C 0
E E E1 1
S C
e s
r s
o a
C l
2 2
2 2
2 2
2 2
C 5
S 5
S S
S S
.o
/
/
/
/
/
/
S
/
N 4
A 4
A A
A
/
A 0
1 2
3 6
1 A
3 0
M e
1 1
1 1
2 3
5 3
E v
1 T
l 4
4 4
e 4
4 4
4 1
S a
1 1
1 i
1 1
1 1
Y v
V V
V V
V V
V V
e-v1 S
RV ti!
l
!l!
fl li llE
0 1
2 3
7 s
2 V
1 k
V
, e G
1 r
l 9
e S
b S
1 s
R a
R e
R T
R G
R d
d d
n n
n a
a a
O 0
0 0
0 3
2 2
3 3
N 2
2 2
2 V
2 1
v V
V V
V V
G Y
G G
G e
N 8
S S
8 S
S t
8 8
1 R
R R
R R
R o
R R
N R
R R
R R
R N
R R
AR e
e e
e e
e e
e e
D e
e e
e e
e e
e e
S S
S S
S S
S S
S sev gi nt J
J J
J i a R
R R
T T
T T
t n R
R R
L L
L L
sr ee T t l
A s
t f s ee V
V T
T T
V V
V i u C
CQMQM L
C C
C l q ee RR s
tnem t e s i
- QMQM C
C r
T T
S V
e T uqe R
n l o a i m t C
C C
C 0
0 0
C O
0 0
r i o s N oP ro t e ap 0
0 0
0 uy A
A A
A t T c
A ee vp K
K A
A A
A K
K K
K K
l y
C C
G G
G G
C C
C C
C eT V
)
82 e.
/
I ie 4
2 4
1 2
4 4
2
/ /
1
/
1 2
1
/ / /
S(
3 1
3 2
1 3
3
/ e ev A_
vi i s A
A A_
A A
A A
A A
A t s ca AP s
c 0
t i
y l
r i
n u
ec C
x x
x x
x x
x U
a va r
l e
l d
at B
x x
x x
o y
Va r
H C
t A
x x
x x
n e
o v
s C
i e
r t
c D
a i
n o
i l
d u
d 8
6 6
8 1
6 2
2 a
R r
1 1
1 1 2, 6
21 1
1 1
r o
- - 0 0
d l
o C
8 C
CB1 D
J81 B
E E
y o
C r
H t
s 9
n s
o a
8 C
l 2
2 2
2 2
2 3
3 2
2 2
r C
o f
4 5
e 1
E 0
e o.
1 1
2 2
/
B 3
B B
l 1
1 1
1 A
A
/
1
/ /
a e
1 1
1 1
e 6
1 1
1 N
2 3
A A
A c
3 3
3 3
3 3
l 2
3 2
3 i
0 M
p 1
E v
3 3
l 1
4 4
y T
l 3
3 3
3 V
V
)
0 0 0 S3 3
T
. 5 D
1 F R 4 C
F)
(
7
/ /
2 a
S
j i) lI j'
7 2
t hS e
t s
t k
i r
S e
. )
s e
E_
R
.o 9
0 0
N 2
3 3
V v V G
N S
S s
I A
A n
s
.e R
A a
uN e e e e e e S
S S
sev' gi a'
nt t
R i
u t n f
R sr ee Tt l
A s
t f s ee T
V V iu M
C C
l q eo pR s
tnem t e sr T
T T
T ei OM 9N 0
- 4N 0M T uqe R
n l o ai mt ri C
C 0
C C
C C
os NoP ro t e ap 0
o 0
0 O
uy
'A N
H A
A tTc
.A ee vp t
t l
K K
A A
l y e
e e
C C
G G
eT V
e.)
zn i i 3
2 2
2 2
1 1
S(
/oew vt is A
A A
A A
A A
t n ce a
AP n
i l
D o
v o
r
. C eo C
x x
va n
l e
. m m
o et x
m m
i VelB t
C I
e A
lc s
l n
e
. i ta e
n r
i o
d 5
2 3
4 0
0 C
r 1
T 1
1 1
1 1
o r
o 0
0 0
K K
N N
o C
t c
e a
s e
o R
l 2
2 2
3 2
3 3
C 0
v 2
3 8
a 8
1 2
o 3
1 1
3 3
G.
0 3
M e
1 1
0 E
v s
7 1
3 3
1 1
1 t
T l
3 3
r 3
3 V
V S
e 1
1 u
1 1
C C
v2
.1 Y
V V
V T
V V
L L
e-S RV ll i
!I
,t,_
. i>i i'.ji i'
I 3
=
~
~
L t
hS 7
s 1
k 1
r 9
e 1
s e
G R
G
.o 3
3 N
V V
.G C
N e
S l
R A
fn.
R R
am.
e e O
e e S
S sev gi nt J
J i a T
T n
L L
t's r ee t
- l. l
.A
~
s t
t s
. V V
ee i u
.C C
l q ee RR s
tnem~
t e sr oi l uqe R
e t o' ei et ri C
C os N oP ro t e ap uy i
t T d
c e
A un ee i
t vp K
K n
l y1 o
aT
.C C
C V
(
)
l an' g
e.
or t i 2
2 t
S(
n Il o
C fe' ev e
yi r
l s A
A
. W t s cr AP t
I e
' D t
y A
r eo C
a u
d vg n
l e l'
a at B
Va t
C i
n A
m m
e m
s n
e i
t a
t an n
i o
d 1
1
. C r
1 1
o
'v o
J J
r C
em s
i s
r a'
P l
C C
C 1
2 o
5 5
e s
9 9
M e
1 1
0 E
v 1
T l
6 6
S a
1 1
3 Y
V V
V v2 S.
e-RV
?
i,l1l!!
!l l
l
- i.,ii' 1
1 3
s 2
k 1
r e
1 s
e N
R 0,
4 0
3 1.
V G
I S
I d -.
R I
l R
A R.
e D
e S
.s
. ev gi nt i a
'~
t n
~
sr ee Tt
.l
. A s
t f s ee V
iu C
l q ee RR s
tn
- e
. m
. t e sr V
ei C
T uq
.e
.R n
l o ai mt ri 0
C os NoP r
. o t e ap uy t T c
. A ee vp K
X
. l y C
C aT h
V
)
e.
zn 4
i i 3
/
. S(
3
~. /e l,
g ia' I
ev vi is A
A
. t s ca AP y
I D-y g
r n
en lC x
x i
ve I,t I
}
l e o
at B
o va 4
C
. C A
CA s
V e
H t
.a m
n o
i o
.d 1
1 R
r 1
1 o
l o
J J
t C
r t
s n
s o
.a C
l 3
3
.C
.o N
A A
5 0
- 3
. e G
6 1
E v
T
. l W
W 6
S a
C C
v2 Y
V S
S o-S
[
?
.lt
!I t9
1Q j
RELIEF REQUEST BAS 85 l
1
-l K
' NUMBER:.
V21 l
SYSTEM:
Co' trol' Rod Drive Hydraulic.
n
'l VALVE:
V3-13-115
{
+
. CATEGORY:
C E
I CLASS:
2 1
FUNCTION:
Control Rod Drive Scram
]
TEST REQUIREMENT:
CV-
~
' BASIS FOR RELIEF: Closure verification of these valves requires that the=
control rod drive pumps be stopped to depressurize the charging water header. This test cannot be performed during l
j.
power operation because stopping the pumps results in a loss
'{
of cooling water to all control rod drive mechanisms and seal
'i L
damage could result. Additionally, this test cannot be per-formed during'ench cold shutdown because the control rod drive pumps supply seal water to.the reactor recirculation
~!
pumps.
I ALTERMATE TESTING: Vermont Yankee performed the above described pressure decay leak test during the 1989 refueling outage. This was the i
first test of this kind performed since origbal plant start-up in 1972. Results of the 1989 test were very similar'to l
the 1972 test.
(Note: Valve leakage'is determined by depressurizing the charging water header and observing accu-J mulator pressure decay corresponding to each 115 check valve.
During the 1972 startup test, accumulators maintained pressure for at least 16 minutes.
1989 test results showed the worst case accumulate,r pressure decay to-be a decrease to I
920 psig after 18 minutes which is still well above the acceptance criteria pressure of 800 psig. Therefor e, the exceptional leak-tight integrity of these valves was recon-
-i F
firmed after 17 years of operation.)
d Sased on the Wove, valve closure will be' verified on an alternating rer'uelirig :.sutage basis by stopping.the control rod drive pumps and otsserving control rod drive accumulator pr ersures. Proper valve closure will be demonstrated by i
- r. accumulators maintaining adequate charging pressure for 5 minutes after the pumps are stopped.
Rev. 10 V-55 1
l
RELIEF REQUEST BASIS-NUMBER:
V30 SYSTEM:
i.
Reactor Core Isolation Cooling VALVE:
V13-70, V13-133 CATEGORY:
C
-CLASS:
2 and 3 FUNCTION:
Gland Seal Condensate Pump Discharge Check Valves TEST REQUIREMENT: CV BASIS FOR RELIEF:
Proper operation of this pair of valves, which are installed in series, cannot be individually verified in the closed direction due to the piping arrangement.
ALTERNATE TESTING: Valves will be verified to open during normal Reactor Core Isolation Cooling surveillance testing.
Closure of at least one valve in the pair is confirmed via continuous monitoring of Gland Seal Condenser level.
Since these valves cannot be isolated without affecting system operability and based on the above monitoring, verifi-cation that each valve functions in the closed direction will be performed once each operating cycle via disassembly or other positive means.
Rev. 10 V-65 i
I' f
I L
^,'
RELIEF REQUEST BASIS i
i NUMBER:
V34 SYSTEM:
. Control Room Ventilation Cooling'
' VALVE:
SCW-8A-CATEGORY:
C CLASS:
3 FUNCTION:
Chilled Water Pump Discharge Check Valve TEST REQUIREMENT:
CV BASIS-FOR RELIEF: Valve cannot be exercised closed during system operation since this would require isolation of the Control Room Chilled Water system and related ventilation equipment.
ALTERNATE TESTING: Valve opening is demonstrated by normal system operation and pump surveillance testing. Closure will be verified annually as climatic conditions permit via valve disassembly or by placing the system in an alternate configuration and observing appropriate system pressure indication.
Rev. 10 V-69
W RELIEF REQUEST BASIS GV-3 Listing ~of Systems and Valves SYSTEM VALVE l-Service and Instrument' Air V72-38A/B, V72-89B/C, V72-103 Reactor Building Closed Cooling Water V70-113, V70-117 Nuclear Boiler V2-27A/S, V2-28A/B, V2-39, V2-40, V2-74, V2-77, V2-80A-D, V2-86A-D, V2-96A/B
. Core Spray V14-5A/B, V14-11A/B, V14-12A/B,
'l V14-13A/S, V14-26A/B High' Pressure Coolant Injection V23-15, V23-16, V23-25, V23-56, V23-62, V23-65, V23-842, V23-843, SSC-23-12, SSC-23-13, Control Rod Drive V3-181, V3-162A/B, V3-412A/B, V3-413A/B Residual Heat Removal V10-16A/S, 'V10-17, V10-18, V10-19A-D, V10-25A/S, V10-26A/S, V10-31A/B, V10-32, V10-33, V10-34A/S, V10-38A/B, V10-39A/B, V10-46A/B Reactor Core Isolation Cooling V13-15, V13-16, V23-27, V23-29, V13-38, V13-41, V13-50, SSC-13-9, SSC-13 Primary Containment and Atmosphere SB16-19-6, SB16-19-6A/B Control SB16-19-7, SB1G-'19-7A/B, SB16-19-8, SB16r19-9, SB16-19-10, SS16-19-11A/B, V16-19-12A/S, V16-20-20, V16-20 22A/B, V16-19-23, V16-19-51, V16-19-52 l
Reactor Water Cleanup V12-15, V12-18, V12-68 Redweste V20-82, V20-83, V20-96, V20-95 Containment Atmosphere FS0-109-75A1,2, Dilution FSO-109-75B1,2, FSO-109-75C1,2, FSO-7501,2, VG-75A3,4, FSO-109-76A/B, VG-23, VG-34, VG-25, VG-26, VCi-33, VG-34, VG-9A/B, VG-22A/B, NG-11A/B, NG-12A/S, NG 't3A/B _
TIP Ball A-C Rev. 10 V-80 2
1 NOTES
- 1..A minimum of 1/2.of all safety valves shall be bench-checked or replaced with a bench-checked valve each refueling outage.
Both valves shall be i
checked or replaced every two refueling outages. The lift point of the safety I
valves shall be set as specified in Technical Specification Section 2.2.B.
1 2.
A minimum of 1/2 of all relief valves shall be bench-checked or replaced I
with a bench-checked valve each refueling outage. All four valves shall be
'l checked or replaced every two refueling outages. The set pressures shall be as specified in Technical Specification Section 2.2.B.
3.
Prior to quarterly exercise and timing tests, decrease reactor power to less than 75 percent. At least twice a week, the MSIVs shall be exercised by partial closure and subsequent reopening.
4.
During each refueling outage, explode one of the three charges manufactured in the same batch to verify proper function.
Then install the untested charges in the explosion valves.
5.
Proper valve operation is shown both by the decrease in pump discharge pressure upon opening of valves V10-16A-D and by proper automatic closing of V10-16A-D at approximately 2000 gpm.
6.
Valves are passive unless the pumpback system has operated during the cycle.
7.
Each refueling outage, each valve will be tested to determine the force required to open each valve from fully closed to fully open.
8.
Only one valve in each line is required to be operable per Tech. Spec. Table 4.7.2.b.
9.
Each refueling outage, each valve will be testod to verify that the setting is between 1400 and 1490 psig.
- 10. Vahes V11-16 and V11-17 shall be leak tested each alternating refueling outage. Valvee V10-18 shall be leak tested each refueling outage. Maximum leakage lirAt s, hell be 1.0 gpm at 101815 psid.
- 11. Valves V23-65 end V13-50 will also be disassembled and inspected at least once every 10 years.
(LER 87-18 and NRC Inspection Report 50-271/87-21).
- 12. Testing of V3-13-138 is not required when the corresponding control rod has been declared inoperable and its directiona'l control valves disarmed per the provisions of Technical Specific 6 tion 3.3.A.2.
Rev. 10 V-81 i
ATTACHMENT 3 i
l l
- g..
- i.
p INSERVICE TESTING PROGRAM FOR VERMONT YANKEE NUCLEAR POWER CORPORTION Revision 10 r
Description, Program, Testing Schedules and Relief Requests Prepared by:
8-
~
C. Kinsey, Pla nservice Testing Coordinator l
Reviewed by:
4
/9 purp46, Senior Mechanical Engineer
/ lfat'e s b& '
hAf
~
M
/ $
f Mejdfl, Engineering Support Supervisor
-/ 'Da(te
. ac* A
%]U
/9hlM Plant Operations feview Committee
/ dat6 V
Approved by:
T
/ 9/7/$i J. $f; Pelletier, Plant Manager
/ Date b
Gy_._
/ l0 S
('
W. P. MurptIy, Mari3ger'of Operations
/ Dat'e i
Rev. 10
INSERVICE TESTING PROGRAM RECORD OF CHANGES INITIALS INITIALS CHANGE DATE CHANGE DATE NUMBER ENTERED PORC PL MGR MOO NUMBER ENTERED PORC PL MGR M0's e
7/29/88 k,,
h'gd
(
bk,
,gf 9a
\\J {
Bf 6-1.
- _).
d
@W i
---__. I.
ii 1
- fJ e
t I
3 hi y;;
l INSERVICE TESTING PROGRAM:
' Table of Contents 4
A, ; General Page(s)
Preface v
14 Preferences vi.
B.-Drawings' D-1 C.~ SectionLI
. Pump Testing Program Scope-P-1 Quantitative Values.
P-1 Symbels P-1 Pump Listing' P-2 Relief, Request Bases:
RRB No. P1 - P7' P-3 to P-10 RRB No. GP-1-- GP-3 P-11 to P-16 al Notes.
.P-17 Table 1 - Qt3antitative Values P D.
Section II.- Valve Testing Program
- Scope V-1 Quantitative Valuts V-1 Symbols and Definitions V-1 to V-3 Valve Listings.
V-4 to V-32 Service Water Reactor Building Closed Cooling Water Recirculation Pump Service and Instrument Air Diesel Fuel Oil Nuclear Boiler 3
iii Rev. 10
__.m._
_____.___m_._a_.m_.-._m_m_.______
5 Table of Contents (Cont.)
Valve Listings (Cont.)
Page(s)
-Core Spray High' Pressure Coolant Injection Control Rod Drive Hydraulic Standby Liquid" Control Residual Heat Removal b
Fuel Pool Cooling Reactor Core Isolation Cooling Primary Containment and Atmosphere Control Radwaste Reactor Water Cleanup System HVAC - Reactor Building Nuclear Boiler Vessel Instrumentation Containment Atmosphere Dilution TIP Relief, Request Bases
-RRB No. V1 to V36 V-33 to V-71 RRB No. GV-1 to GV-3 V-72 to V-80 Rotes V-81 Table 1 - Quantitative Values V-82 to V-84 Table 2 - Valves Tested During Cold Shutdown.
V-85 to V-90 iv Rev. 10 l
f?
l' PREFACE l-The program presented herein is written to comply with the requirements of
,10 CFR 50.55a(g) published in the Code of Federal Regulations dated January 1, 1982.
The applicable Code edition and addenda is the ASME Boiler and Pressure
. Vessel, Code,Section XI, 1980 Edition through and including the Winter 1980 Addenda.
In accordance with 10 CFR 50.55a(g), the 120 - month inspection interval is as follows:
Start Date End Date November 30, 1982 November 30, 1992 v
Rev. 10 i_____-___-___-_-_-_
- o K
REFERENCES 1
i 1
1.
1' 2.
Vermont Yankee Technical Specifications, Section 4.6 (as revised by Amendment 99).
3.
ASME Boiler.and Pressure Vessel Code, 1980 Edition, through and including.
the Winter-1980 Addenda.
4.
-Letter, Mr. V. L. Rooney, USNRC, to# r. R. W. Capstick, VYNPC, "
Subject:
M l~
Request for Additional Information - IST Program", Docket 50-271, NVY l
87-01, dated January 5, 1987.
5.
Letter, Mr. V. L. Rooney, USNRC, to Mr. R. W. Capstick, VYNPC, "
Subject:
Meeting Summary", Docket 50-271, NVY 88-074, dated May 9, 1988.
6.
Memo, J. C. Kinsey, VYNPC, to J. P. Pelletier, VYNPC, "
Subject:
Revision of Vermont Yankee Inservice Testing Program, Revision 9," dated February 27, 1989.
7.
Memo, J. C. Kinsey, VYNPC, to VYNPC Distribution, "
Subject:
Implementation of.IST Program Revision 10 Changes," dated August 16, 1989.
vi Rev. 10
SYSTEM FLOW DIAGRAMS FOR SAFETY-RELATED SYSTEMS
'The following drawings are provided with the:IST program submittal for NRC review only:
(NOT included in In-house copies)
G-1911159 Shts. 1,2,3 & 5 Service Water System G-191160 Shts. 3,4,6 & 7 Service and Instrument Air G-191162 Sht. 2
' Miscellaneous Systems G-191167 Nuclear Boiler G-191168_
Core Spray System G-191169 Shts. 1 & 2 HPCI System G-191170 Control Rod Drive Hydraulic System G-191171 Standby Liquid Control G-191172 Residual Heat Removal System G-191174-Shts. 1 & 2 RCIC System G-191175 Primary Containment - Atmospheric Control G-191176 Condensate and Demin. Water Transfer G-191177 Sht. 1 Radwaste System G-191178 Shts. 1 & 2 Reactor Water Cleanup System G-191237 HVAC - Control Room G-191238 HVAC - Reactor Building G-191267 Nuclear Boiler Vessel Instrumentation VY-E-75-002 Containment Air Dilution System 5920-4146 Emergency Diesel Generator Starting Air D-1 Rev. 10 u-______
?
l SECTION I INSERVICE OPERABILITY TESTING PROGRAM FOR PUMPS SCOPE:
i l
This program describes the inservice operability testing of pumps to meet the requirements of Section XI of the ASME Code, Subsection IWP, " Inservice Testing of Pumps in Nuclear Power Plants".
Inservice operability testing is required for Safety Class 1, 2, and 3 centrifugal _and displacement type pumps that are installed in light-water cooled nuclear power plants and that are required to perform a specific function in shutting down a reactor or in miti-l gating the consequences of an accident and are provided with an emergency power source.
L All specific required testing ~and examination procedures required by this program including schedules, the location and type of measurement for each of the required test quantities, records of the results, acceptance criteria, and all corrective action taken shall be developed and maintained by VYNPC.
Relief Requests from certain ASME code requirements are located in the back portion of this section.
QUANTITATIVE VALUES:
In addition to the reference values and allowable ranges established per IWP-3110 and IWP-3210, respectively, and the Relief Requests contained herein, quantitative values are established for certain test quantities. These values are based on the Plant safety Analysis and are included in Table 1 of this sec-tion.
SYMBOLS:
The following symbols are used:
N Pump Speed, RPM Pi Pump Inlet Pressure, Psig Pump Differential Pressure, Psid AP Pump Flow Rate, GPM Q
V Pump Vibration Level, Mils or In/sec. See Relief Request Basis Number RRB-GP-3.
LL Pump Lubricant Level, In Lp Pump Lubricant Pressure, Psig Quarterly Testing in accordance with IWP-3400 QT P-1 Rev. 10
S e
e l
K e
l l
b R
l b
b a
A b
a a
T M
a T
T
/,
E T
/
/
1 4
6
/,
3, 3,
3, P
P R
e
, 3, 3,
1 1
1
,l 1
1,
2b 3
5 7
1 P 2, s
s epa s
eP2P P 2, e
e l
T e
l B1 t
t bB/
t bB1B B1 R
o o
aR1 o
aR R1R R s N
N T R N
TR sR R s e
e e
e e
et e
e eet e
eet et et eo e
e eeo e
eeoeoeo SN S
S SSN S
SSNSNSN S
LS PVELR P
L L
r P
oBUR SLLO E
I T
I R
T VB V
V V
V V
V V
V V
V N
I A
V UQ W
T QO Q
Q Q
Q Q
Q S
L E
F T
E C
S I
S P
P P
P P
P P
V PE A
A A
A A
A A
R AR E
P SN I
TS iES i
i i
i i
i i
i PLE P
P P
P P
P P
P NR I P D
E NE N
N P
S l
I i
YTY I C LN I E BU T
T T
T T
T T
T T
T AQ Q
Q Q
Q Q
Q Q
Q Q
Q RE ER PF O
3 2
2 2
2 2
3 3
3 AL SC E
CG9 92 292 1
8429 2
7 NN5 5/
76/
7 67/5 6
3 EI 11 1 1 1 1 1 1
1 11 1 3 1
2 RW1 1
1 1 1
1 1 1
1 1
99.
9 99 9
9 EA9 9
. 9 FR1 t 1 t 11 t 1
1 1t 1 t 1
1 ED - h - h
- - h
- - h - h R
GSGS GGS G
GGSGS G
G M
I S
C 0
E W
C C
I F
T S
P C
S D
HB B
RB B
Y DD
/
/
/
/
C S
A AA A
AA A
A
/
AAW1 1 1 1
11W 1
V P
1 1 S -
- - C 1H M
- - R0R 45C 6
79C 2 -
U 78H1 H 4 4L 4
4 5 B 9PR P
PPRPR PPS P
i
i'
./;
i Relief Request Basis-H p
. NUMBER:
P1 I-SYSTEM:
. Service Water L
' PUMP:
P7-1A-D CLASS:
3
- TEST REQUIREMENT ~
Quarterly testing per IWP-3100
' BASIS FOR REQUEST:
For these pumps, neither inlet pressure nor flon rate can be directly
. measured.
Inlet pressure can not be directly measured as these pumps are of the
. deep'well,' centrifugal turbine type.which rely on intake structure water level for suction head..
Flow rate can'not be directly measured due to the absence of sufficient straight piping to' allow'for instrument installation.
In lieu of direct measurement, flow rate, differential pressure and total discharge head are calculated using a computer program which fits a head / capacity curve from the data-inputs of intake structure water level and
- temperature and pump discharge pressure.
The results are evaluated against the quantitative values given in Table 1.
'Since flow can not be throttled nor differential pressure fixed, (dependent on river water levels and temperatures and system heat loads) the data received from the' computer program may not be a true indication of the pump's perfor-mance. Vibration' levels are also subject to change since the reference para-meter'of differential pressure can not always be achieved.
7 P - 3 Rev. 10
2 1:
. ALTERNATE' TESTING:
Portions of the Service Water system will be isolated during each refueling
- outage and all'four Service Water. pumps will be subjected to a full flow test using temporarily. installed flow instrumentation. Data from this test will be-evaluated against.the values given in Table 1 and will be used to calculate a
. revised head / capacity curve. This revised curve will then'be'used in the per-formance evaluation discussed above using quarterly readings, and will be ana-
~
lyzed.for trends to the degree possible.
I..
In addition, the current practice of taking one pump out of service.during 1
each operating cycle for preventive maintenance overhaul will be continued.
P - 4 Rev.. 10
y
, p
- p. ~
o L'
Relief Request Basis-i-
.f.
/NUMBEkc P2 SYSTEM:
Standby Liquid' Control PUMPS.
P45-1A/B CLASS:
2 TEST REQUIREMENT:
Reference values per IWP-3100, Table 3100-1 BASIS.FOR RELIEF:
In accordance with Table IWP-3100-1, flow will be measured from flow' element FI-11-1~.
This parameter will be established as the reference value and trends analyzed per IWP-3100. Differential pressure will not be measured as it I:
is variable since suction is from a vented tank.. Inlet pressure will only be measured to assure that there is liquid in TK-21-1A, as not to damage the pumps.
ALTERNATIVE TESTING:
Continue testing and analysis of flow and vibration results per IWP-3200.
.J P-5 Rev. 10 6-E
_:_ _. = __ _ =_ __ _ _ _ _ __
{'-.
ug
'------~T-L m,.'
'4; s
? 1
' W L;
1,
. Relief Request Basis-r.' p.;
!M
' NUMBER:.
P3 '.
V+
SYSTEM:
. Reactor' Building Closed Cooling Water
- PUMP:
P59-1A/B; J.
[:r;,
CLASS:
'3 TEST REQUIREMENT:
. Proper,1ubrication level and or pressure' per 'IWP-3110 Tat le W.,
l i::
- IWP 3100-1.
e.:
a l
BASIS FOR RELIEF:
H,m.
iPump has' grease. packed bearings and therefore cannot be checked.
o i'.'
'e
'~ ALTERNATIVE TESTING:
..s..
None.
v,,
N.
}
);
i! -
'e.,
l' P-6 Rev. 10
w;c
- y 6
,ll 7
1 s
'i
.F c
(
N'
~
<iC$
l m
g'
~ '
. Relief' Request. Basis o.@
- 1. = 1,
pp.
p
- NUMBER:
SYSTEM:
Reactor Building: Closed Cooling' Water d
1
' PUMP:
-P59-1A/B-CLASS:
3 c,
r:
. TEST REQUIREMENT:
Inservice test quantities per IWP-3100, Table IWP-3100-1 I
L
' BASIS FOR RELIEF:
Table IWP-3100-1 specifies the Inservice Test Quantities to be measured or
')
F 1
i observed. Differential pressure varies due-to the distribution of' cooling water l
=to;the various loads as regulated by temperature and pressure control valves in.
)
'l
[C Inlet pressure also cannot be measured before the pump test since.
.the. system.
Lthe. pumps are normally: running. The. vibration levels are also subject to I
I fchange since the reference parameters cannot'always be achieved.
-]
r ALTERNATE TESTING:
' Quarterly readings will continue to be taken, recorded, vnd analyzed for l
-trends to the degree possible.
Due to the variation of cooling water-distribution referenced above, flow testing'must be performed at a climatic condition producing a reference pump discharge pressure.
Therefore, full flow testing will be performed once per year as-climatic conditions' permit.
l 1
(Note: Since pump flow indication is not currently available, it will be incorporated no later than the end of the 1990 refueling outage.)
P-7 Rev. 10
______-____-__-________-_O
g% w t u n.-y. ;. :
- - - - - - - = ' - - - ' ' ' -
~
~ - - - -
p
=;
%.n,. '
4 M
1 1.
- m ',
- h,')
~ Relief Request Basis 4
'U p
[ NUMBER' P5
,.po
-SYSTEM:.
Fuel.011 Transfer.
PUMP:
P92-1A/B
.su CLASS:
3 J.
L' TEST REQUIREMENT:
Proper lubrication.and or pressure per IWP 3110. Table
IIWP-3100-1.
i^
- BASIS.FOR RELIEF:
Pump has grease-packed bearings and therefore cannot be Us checkhd.
IJ
' ALTERNATIVE TESTING:
None.
[:.s t
O:
u t,
P-8 Rev. 10 l_________________________2-__-__--_---_-_-_____--____
_ _ _ _ __ _ a
p Relief Request Basis NUMBER:
- SYSTEM:
Fuel Oil Transfer PUMP:
P92-1A/B CLASS:
3 TEST REQUIREMENTS:
Differential pressure and flow measurements per IWP-3100, Table IWP-3100-1.
BASIS FOR RELIEF:
Fuel oil pumps are positive displacement pumps which are in a fixed resistance system. Per Table IWP-3100-1, Note 1, it is required to measure dif-ferential pressure or flow rate. There is no method available for measuring flow. Differential pressure varies with the amount of fuel in the diesel fuel storage tank, TK-40-1A.
The differential pressure is also subject to viscosity changes of the fuel oil due to seasonal temperature variations. These variations are not indicative of positive displacement pump performance.
ALTERNATIVE TESTING:
. Ensure that each pump is capable of supplying fuel oil to the day tanks at a flow rate greater than that required by the associated diesel generator under full load operation. This shall be verified by an increase in day tank level during each surveillance test of full load operation.
In addition, once per operating cycle, day tank level will be reduced to allow for a pump flow test. Day tank level increase will be measured versus pump operating time to calculate a flow rate. This rate will then be trended and analyzed.
P-9 Rev. 10
m.
LU w
< a y
L Relief Request Basis
' NUMBER:
P7 SYSTEM:
Control Room. Ventilation Cooling PUMP:
'SP-1 CLASS:
3 4
TL'ST. REQUIREMENTS: Inservice. test quantities per IWP-3100, Table IWP-3100-1 L
BASIC FOR RELIEF:
f Per response to USNRC Generic Letter 89-04, " Guidance On Developing Acceptable Inservice Testing Programs," Vermont Yankee committed to adding the Control Room Ventilation system to the IST program.
In addition, since' flow indication is not presently available for pump SP-1, it was committed to be
. incorporated no later than the end of the 1990 refueling outage and tested quar-
- terly thereafter.
ALTERNATIVE TESTING:
~Until; flow ~ indicating equipment.is installed, quarterly pressure and vibra-tion readings will be taken, recorded, and analyzed for trends to the degree possible.
)
L E
P - 10 Rev. 10 l
' j.!
t 1
o..
L..
Relief Request Basis
]
1 NUMBER:
GP-1 CODE PARAGRAPH:
Table IWP-3100-2 TEST REQUIREMENT: Allowable Ranges for 'AP and Q p
i BASIS FOR RELIEF:
. A-thorough review of past operating surveillance data and continuing dif-ficulty in obtaining consistent data-indicates a need to re-evaluate the ranges
- specified in the code paragraph listed above. There are many causes for the difference in readings which have no relation to pump degradation. Differences L-in the manner by which gauges or meters are read, accuracies associated with-each instrument, the affect on the instrument system due to the inaccuracies of each component all contribute to readings that are out of specification by more than 2% allowed by the code.
The nature of the test method required by ASME XI also contributes to the
~
. inconsistent data. When establishing the fixed parameter,'there can be no
- tolerance since errors here will compound the error in reading the' variable parameter. Because'of the' instrument inaccuracies and the test method, the data often unjustifiably falls into the required action level of ASME XI.
These test method induced discrepancies are.not syptomatic of-a pump failure.
Based on.our-experience in surveillance testing since commercial operation in 1972,.the ranges proposed in the following section represent reasonable and expected deviations of the pump parameters.. The proposed changes only expand the range in the more conservative' direction, i.e.,
allowing more flow or a
- higher differential pressure. These ranges are consistent with.our Safety Analysis in that they do not lower the minimum' flow or discharge pressure required.
ALTERNATIVE:
The high end of the various ranges will be adjusted upward as indicated in
. the following table:
Parameter Acceptable Alert Action Q:
.94 - 1.08
.90 - <.94
<.90
>1.08 - 1.12
>1.12 AP
.93 - 1.08
.90 - <.93
<.90
>1.08 - 1.12
>1.12 P - 11 Rev. 10
p:1 RELIEF REQUEST BASIS l
[.
NUMBER:
GP-2 CODE PARAGRAPH:
.IWP-3300 and IWP-4300 l'
TEST REQUIREMENT:
Measurement of Pump Bearing Temperatures BASIS FOR RELIEF:
Paragraphs IWP-3300 and.IWP-4300 require pump bearing temperatures to be measured annually. However, the yearly temperature measurements do not provide a viable means of monitoring pump mechanical condition. First, there are several factees, such as working fluid and ambient temperature, that cea ~fect the pump bearing temperature. This would make detection of pump degradation difficult. Second, it has.been demonstrated by experience that bearing tem-perature. rise occurs only minutes. prior to bearing failure. Therefore, the detection.of possible bearing failure by a yearly temperature measurement is extremely unlikely. :. Third, it requires at least an hour of pump operation to achieve stable bearing temperatures. The small probability of detecting bearing failure by temperature measurement does not justify the additional pump operating time required to obtain the measurements.
This' Relief Request Basis is consistent with the requirements of ANSI /ASME Standard OM-6, "In-Service Testing of Pumps", Draft 11, which does not require bearing temperature measurements.
ALTERNATIVE TESTING:
Pump mechanical condition can be determined much more accurately by measuring bearing vibration.
Paragraph IWP-4500 requires at least one vibration level be read during each in-service test. The number of readings will be expanded to a minimum of two in orthogonal directions..These additional readings, in addition to the revised vibration measurement methods and accep-tance criteria given in Relief Request Basis GP-3, will provide a viable means of monitoring pump mechanical condition.
P - 12 Rev. 10
p d'
RELIEF REQUEST BASIS k
NUMBER:
GP-3 CODE PARAGRAPH:
IWP-4500-l' TEST REQUIREMENT:-
Measurement of Pump Vibration in Mils BASIS FOR RELIEF:
Recent analysis done by the ASME in developing ANSI /ASME Standard OM-6,
" Inservice Testing of Pumps", Draft 11, has found that to more accurately moni-
. tor pump degradation, vibration measurement parameters should be determined by
- pump speed.
Currently, IWP-4500 requires vibration amplitude measurements to be taken in displacement for all pumps, regardless of speed. However, it has been found that although displacement is a representative parameter for low-speed pumps
-(<600 rpm),. vibrational velocity is a more accurate and representative indicator of degradation of higher-speed pumps (> 600 rpm). Velocity measurements detect i
not'only high amplitude vibrations that indicate a major mechanical problem, but also the equally harmful low amplitude, high frequency vibrations due to mis-alignment, unbalance, or bearing wear that may be undetected by displacement j
measurements.
In addition, due to the physical arrangement of the HPCI pump, supplemen-
-l tal limits of vibrational velocity have been developed.
A summary of the deve-j i
lopment of these supplemental limits is included in Attachment GP-3-A.
l l
l I
P - 13 Rev. 10 j
I
__-_ -___ ___--______ _ _ _ _ Q
' ALTERNATIVE TESTING:
The requirements consistent with ANSI /ASME Standard OM-6, Draft 11 will be incorporated into the Vermont Yankee IST, Program for pumps. These requirements, as well as the supplemental limits referred to above, are included in the attached Table GP-3-1.
As a minimum, all measurements will be.taken per the following guidelines:
l a.
On centrifugal pumps, measurements shall be taken in a plane H
approximately perpendicular to the rotating shaft in two orthogo-nal directions on.each accessible pump bearing housing.
Measurement also shall be taken in the axial direction on each accessible pump thrust bearing housing.
b.
On vertical line shaft pumps, measurements shall be taken on the upper motor bearing housing in three orthogonal directions, one of which is the axial direction.
l c.
On reciprocating pumps, the location shall be on the bearing housing of the crankshaft, approximately perpendicular to both the crankshaft and the line of plunger travel.
l l
l I
l l
l l
I P - 14 Rev. 10
R t
I N 0
i UO r
r 7
m QI o
o i
ET 0
l RC p
r p
r>
.A V
V V
V r
6 6
6 6 r e
>o p
pu c
c e
e e
s s
g s
/
/
n l
n n
a i
i i
R m
r r0 p
0 e
V2 V7 V
r7 l
62 6
6 6
b 0
0 a
o>
o>
o o>
t t
t t
t p
t t
t e
ro ro p
ro c
TE Vn Vn V
Vn c
- 5. t
- 5. t 5
- 5. t A
EN LA 2 u 2 u 2
2 u n
>b
>b
>b a
e s
c v
l e
c a
s e
h i
m
/
s n
/
l E
5 n
l i
L i
a S
B 0
5 h
R AE 1
2 5
s E
TG p
p3 p
p7 l
T PN V>
V V
V6 d
E EA 50 n
- 5. t 5
- 5. 0 M
CR a
1 A
C 2 o 2 >
2 2 >
R A
$n 1
5 t
3 A
t t
s P
t o
o e
P u
n n
t G
T b
)
S t
t e
h E
E u
u u
c L
T b
b l
a B
a e
A F
V T
O g
l n
S l
i E
a r
G R
r u
N E
e d
A T
v r
R TE 0
d V SM y
e EA V
m t
3 TR u
a A
d y
dr y
r u1 P
V V
Vo V
t l
c a f e
v o t
p e
n S
t ei e
(
m b m e
y i
c t
n ol a
i o
s l
c i
l r
m m
p o
t a e p
p s
l a
p r
r i
e r
l p
D D
V b
l u
PE 0
0 i
a ME 0
0 l
l V
h e U P 6
6 a
a s g P S n
n e
n o
c c
s a i
i n
k R t
t e
a a
a r
et r
r e
p r b
b f
e e
el
)
i i
g p
V V
R c A l
n m
n l a i
u
=
=
=
a n act t
p n a gif a
d y
p o
ut a c
P V
V V
sd f rh o
H e n i eS r
(
R a rV p
P E t
e i
I E
M P nd n c
C T
U Y eni e
P O
P T C aL R
H N
[
ATTACHMENT GP-3-A Past testing and analysis performed on the High Pressure Coolant Injection (HPCI) system by VermontfYankee, the pump manufacturer, and by independent vibration consultants has revealed characteristic pump vibration levels which exceed the acceptance criteria stated in ANSI /ASME OM-6, Draft 11.
The root causes of the higher vibration levels have been determined to be:
- 1) An acoustical resonance in the piping connecting the low pressure and high pressure (HP) pumps, and
- 2) The presence of a structural resonance in the horizontal direction on the HP pump.
These resonance conditions are design related and have existed since initial pump installation. They have been documented over a number of years of operating experience.
An additional past contributor to the higher vibration levels was the excitation resulting from the blade pass frequency from the previously installed four vane impeller in the low pressure (LP) pump.
In an effort to reduce / eliminate this effect, the four vane impeller was replaced with a five vane impeller during the 1989 refueling outage.
This replacement significantly reduced vibration levels in both the LP and HP pumps. However, due to the resonant effects referenced above, HP pump vibration levels remain higher than the acceptance criteria stated in ANSI /ASME OM-6, Draft 11.
Although existing vibration levels in the HP pump are higher than standard acceptance criteria, they are acceptable and reflect the unique operating characteristics of the HPCI pump.
It has been concluded that there are no major vibrational concerns that would prevent the HPCI pump from performing its intended function. Therefore, to allow for practical vibration monitoring of the HPCI pump, alternate vibration acceptance criteria are required for the HP pump. Standard acceptance criteria per ANSI /ASME OM-6, Oraft 11, are applied to the LP pump.
The following criteria will be used for the HP pump:
Test Parameter Acceptable Range Alert Range Required Action Ranae Vv f 2.5Vr
>2.5Vr < Vv $ 6Vr Vv > 6Vr but not >0.675 in/sec but not >0.70 in/sec or >0.70 in/sec In addition, the resonance peaks will be evaluated during each test and will have an Acceptable Range upper limit of 1.05 Vr and an Alert Range upper limit of 1.3 Vr.
P - 16 Rev. 10
__-_ ____ - -__ _ w
fi:
NOTES-u
,1..Non' variable speed pump. Speed is not applicable per IWP-3110, Table'-
'IWP_-3100-1..
-2.-
Initial suction pressure cannot be taken due toLthe fact that pumps.are nor-mally running.
3.
Lubricant level or pressure observation is not necessary since pump bearings
.are lubricated by pumpage..
d P - 17 Rev. 10 1
d
1]
1 7
N 0
1 WL R
OL E
LA T
v EH A
e BS W
R L
NP E
8 HM C
1 TU E
I
,P Y
E E
G V
C G
L A
R YE N
A C
T E
P LH
.E T
Y U
S ET U
U C
O V
Q 0
0 O
0 0
R I,
E 0
0 G
0 G
0 H
TT R
4 4
G N
4 N
4 R
CE F
3 3
N I
3 I
3 EM I
T L
F P
.Y P
P L
A P
.E P
O SE T
W W
E R
W U
W EB I
I I
U E
I F
I S
R L
F P
E R
T I
R R
E 0
R R
R I
,O B
E E
R
/
E E
A 0N A
P P
E P
. H P
P 1
R
'H C
C 2N E
C N
A G
3A P
A O
E N
- C O
E I
P D
WS N
IE O
U P
DL S
NA E
AV R
E R
E R
0E T
KE T
O 1S A
NT A
C 1E P
P S
AA S
3H U
U N
1W N
E
- T E
E E
E H
P N
N D
TD
.S D
T WF I
I L
N SE U
N I I L
L E
O EZ R
OK N
H S
CK TI O
CN E
R T
M M
S N
L T
A H
E.
A E
E E
OA OA OT W
PS P
T T
V TT TR O
T I
S S
E T
E T
DS W
Y Y
O EE EN EG E
EY O
S S
T TG TI S
TA L
HL L
AR T
SA F
L L
L LR LE R
LO U
IN A
A E
UO UD O
UT O
1 LA M
M S
CT C
T CS B
R R
S RS RG R
R
- E AY.
O O
E I
I N I
E L
TT N
N V
C CI C
T B
SE E
ES E
A~
A EF R
RU R
W T
A SS EG E
ER P
E SE E
E
- P LE' F
RO BH M
R E
AT 0
E O
GE W
5 E
T T
NR
.R S
C AA ON S
2
- U Y
AE H
LO T
L N
F S
O A
S G
I RU XP E
M I
LE I
AS S
EM DS E
H S
AR S
P LS U
NA MR D
P MP P
R S0 MR A
MU O
M OG 5
T P
NN 7
I1 O
HE EE NE G
I 2
A-NG T
UH IR T
T TT 1
GF N
S A
N 5
R T
AT R
VL O
I M
1 ME A
MD A
E B
L A
G G
1 GO M
P H
GP TV 0
0 0R G
0 O
R NS M
0 5
5O 0
0 TE EE'.
P 7
4 2T 5
0 0
AS REEE G
2 7
4C 3
3 4
FRV A
DN EAI.
0 E
EO R
T 0
R RI SA 7
M OVN M
S R
C D
T I
E R
H I
L S
C EN E
T W
H R
C S
C I
RA NVD S
S R
P C
U OIE Y
D H
B B
S D
D
/
/
SP TAA
/
A A
A A
A EM I TL P
A A
1 1
1 1
1 RU DIC M
1 1
PP DTE U
0 4
5 6
7 ANO P
7 8
1 4
4 4
4 A
P P
P P
P P
llllL
SECTION II l
f l
INSERVICE OPERABILITY TESTING PROGRAM FOR VALVES SCOPE:
This program describes the inservice operability testing of valves to meet the requirements of Section XI of the ASME Code, Subsection IWV, " Inservice Testing of Valves in Nuclear Power Plants".
Inservice operability testing is required for certain safety class 1, 2, and 3 valves (and their actuating and position indicating systems) in light-water cooled nuclear power plants, which are required to perform a specific function in shutting down a reactor to the cold shutdown condition or in mitigating the consequences of an accident.
All specific required testing and examination procedures required by this program including schedules, required test quantities and methods, records <f the results, acceptance criteria, and all corrective actions taken shall be deve-loped and maintained by VYNPC.
Relief Requests from certain ASME code requirements are located in the back portion of this section.
QUANTITATIVE VALUES:
In addition to the reference values and allowable ranges established per IWV-3417 and the Relief Requests contained herein, quantitative maximum stroke times are established for certain valves. These stroke times are based on the Plant Safety Analysis and are included in Table 1 of this section.
SYMBOLS ANO DEFINITIONS:
The following symbols and definitions are used:
Cateoory A Valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their function.
(IWV-2200)
Tests Q
Exercise the valve to the position required to fulfill its function every 3 months.
(IWV-3400)
MT Measure stroke time at the same frequency of the valve exercise (not more often than 3 months).
See Relief Request Basis Number RRB-GV2.
LT Leak test the valves at least once every 2 years.
(IWV-3420)
V-1 Rev. 10 l
______________-__--____n
u,, r n
i Cateaorv'B Valves for which seat leakage'in the diosed position is incon-sequential for fulfillment of their function. (IW-2200) i i
Tests
-Q Exercise the valve to the position required to fulfill its function every 3-months.
(IW-3400)
MT Measure stroke time at the same frequency of the valve j
exercise (not more than 3 months). See Relief Request Number RRB-GV-2.
Cateaory C Valves which are self-actuating in response to some system characteristic, such as pressure (relief valves) or flow direc-I tion (check valves).
(IW-2200)
Tests CV Exercise to the position required to fulfill its function every 3 months.
(IW-3520)
SRV. Test safety and relief valves to the frequency established in Table IWV-3510-1.
ST Test safety and relief valves in accordance with ASME PTC 26.3-1976 every 2 years.
(IW-3510)
Cateaory D Valves which are actuated by an energy source capable of only one operation, such as rupture disks or explosive actuated valves.
(IW-2200)
Tests
~ DT.
For explosive valves--remove, fire and replace 20% of the charges every 2 years.
(IW-3610)
For rupture disks--test in accordance with the manufacturer's instructions.
(IW-3620)
Test Requirements
.LTJ Leak Rate Test, documentation and analysis will be completed in accordance with 10 CFR 50, Appendix J.
See Relief Request Basis Number RRB-S 3.
RR Exercise valve for operability every refueling outage.
CS Exercise valve for operability every cold shutdown.
RA Rapid Acting Valves. A maximum limiting stroke time of 2 seconds is established. See Relief Request Basis Number RRB-GV-2.
Valve Types GA Gate valve GL Glove valve CK Check valve i
V-2 Rev. 10 I
nv gi "a'
k.
(
~,{,,
Q-
.EFC Excess Flow Check Valvea b.
RV. Relief or Safety Valve
'.RD. Rupture Disk-L
.BF Butterfly Valve U;
ll' BL Ball Volve Actuator Types
..d^
'h0- : Air. operator, M.
Manual-lr; l: / '
.MO Motor operator __
EXP Explosive
-SO.
- Solenoid operator.
- HO' Hydaulic operator Active' Valves'.' (A) Valves'which'are required to change position ~to accomplish
.'a specific: function..
Passive' Valves (B) Valves.which are not required.'to change position to ~
accomplish.a specific function.
ll' i,
- ifg L.
o i
i V-3 Rev. 10
. - _ - - -. - - - - - _.. -. - - - -. - _ _ - _ - - - _. _ _ - - - - = - - - - - - - - - - - _ - _ - - - _.. - _ _ _. - _. _ - -
.__----___--.__-._--_.-____.-_.--________------__.-_-_-_--------._-.-__A
ji
,1 i,
- q y_
t 1
th S
9 s
1 n.
k 1
r 9
a 1
me 5
. R D
5 0N 1
2 3
V V
V G
N B
B B
I R
R R
g W
R R
R A
R e
e e
D e
e e
S S
S
~
s
. ev gi nt i a R
^
. t n R
sr ee
~
. Tt l
A s
.t f s ee V
~
V T
i u C
l q C
M ee
. RR s
tne-m t e
. T
- T V
V V
sr ei
-QMQM C
C 0
C T uqe R
n l o ai mt
~
ri 0
O O
C C
0 C
C os NoP ro t e ap' O
O O
. uy M
M S
t T c
A '
ee vp K
A A
K K
K A
K l y C
G G
C C
C G
C aT
- V
)
e.
4 4
zn 4
4 0
2 2
8
/
/
. ii 1
2 2
1 1
3 3
.S(
/ e ev' vi'
. is' A
A A
'A A
A A
A t s ca AP D
v i
e w C
x x
x x
X v e l
at B
x x
X VaC A
se t
r a
n 1
3 3
2 t
i 3
1 1
1 1
a d
2 1
W r
H.
H.
J.
J.
I.
1 1
9 o
2 o
B B
F A
B B
K L
c C
iv s
r s
e a
S l
3 3
3 3
3 3
3 3
C.
B B
B B
D o.
D
/
/
/
/
X M:
N.
A A
A A
A1 A
9 0
8 0
3 48 0
e.
1 1
2 3
4 4
1 1
E v
0 s
a.
h 0
0 0
0 0
70D T
l 7
7 7
7 7
7 E7 -
v4 1
V v
V V
V V
V SVA e-3 i
l>l' J 7
l1q,l
}i!
,5.g~'1.
lJI j
z 7'
M
~ -
4'
. 'c
?
~
m~
m w
2 e
3 l
b a
h T
S 9
d n
5 s
a 1
k 1
r 2
1 9
a 1
m.
e e
e l
l G
R.
b b
a a
T T
O 3
3 N
V V
G G
G N
S B
I R
R N
R R
AR e e D
e e
L S
S sev gi nt J
J i a
.T T
t n L
L sr ee Tt lA s
.t f s ee T
T iu
.L L
l q ee RR s
.t nem t' e sr S ST V
ei C CM C
Tu q e
R n
l o ai mt ri' 0
O 0
os NoP ro t e ap O
uy M
tT -
c A'
ee-vp K
A K
l y C
G C
aT V"
)
e.
t n 2
ii e
8 1
S('
re
/e t
ev a
vi W
i s~
A A
A t s~
e ca n
AP i
l nD oo C
e C
x x
d v
e l e s
at B
o Vs l
C C
A x
m a
s n
e i
t
, d a
l n
i i
7 u
d 1
. B r
s 1
5 o
r o
L L
A o
c
. tc s
a s
e a
R l
2 2
3 C
B o
/
M:
M 3
7 A
1 1
5 0
. E v
e 1
1 9
1 T
l 0
0 0
S a
7 7
7 v5 Y
V V
V V
e-S RV i;
I l
i!
l
,l!llllll t
Il
,f!l llll
I\\
,]
g.g I
'i
-:~
. 5 th
'. S
_9
-., 5 s
1 k
1 r
- 9
_e F
I 1
s e
f'.
- G R
_. 3 0
t 0
. 8 4
V
,C 10 S
B 1
R R
42 R
R U
1 e e 0
e e S
S sev gi nt i a R
R t n R
R sr ee Tt l
. A s
t f s ~
ee V
V i u C
C l q ee RR s
tnem
. t e sr T
T ei L
L T uqe~
.R n
l o-ai et ri 0
0 os e o
- l P ro t e ap uy tT
- c '
A ee C
C vp F
F l y E
E aT
. V
)
e.
t n' i i 1
1 S(
/eev vi is A
A t s ca AP
<D vr eo C
x x
vs l e at B
Va e
C_.A x
x su P
a n
.ts o
6 i
ta 5
l u
o c
C r
i s
c s
e a
R l
2 2
C
.o B
s M:
N
/
/
A A
0 e
7 8
1 E
v T
l 2
2 S
a v6 Y
V 2
2 S.
e-RV
[,
E l
e e e e e
e e
e e
e e
e e
e 0
h h
h h
h h
h 6
s S
S S
S S
S S
1 k
1 r
1 2
9 e
1 m
e e o
l l
G R
b b
a a
T T
's, O
3 3
3 M
5 5
V v
V v
V G
G G
G N
R n
n 8
8 W
8 s
m a
I Ma te W
a R
e e
e e
e D
e e
e e
e S
S
.S S
S
~_
se w
J' J
gt n t J
i e
T T
T
~
t n
L L
L s r~
e e T t
. lA s
t f s e e T
T T
T T
i u M
M L
L L
l q e e R R x
s tn em t e V
V T
S s r e i 0
0 C
C QM C
T u q
- e R
- n l' o ai mt ri C
C C
C 0
0 C
o s N o P
ro t e a p O
G 0
u y S
S A
t T
~
c A
ee vp L
L K
K L
K K
g ~
l y G
G C
C G
C C
eT V
)
2 2
e.
k k
/ /
_ irn 4
1 1
i 1
1 2
/
2 S(
3 1
1
/eev
. vi
.i s A
A A
A A
A P
t s I
ca AP 0
r y
i r
A eo C
x x
x x
vg t
l e n
et B
x x
e Va m
C u
A x
x x
r t
s s
e a
t l
a 7
7 4
4 n
d i
1 1
1 1
n d
a r
3.
6, 7
1 1
3 6
1 1
1 o
e o
8 8
E F
E K
K c
C i
v s
r s
~
e a
S l
3 3
3 3
2 2
2 C
o.
D 0
8 C
/ /
M:
N B
8 A
A A
8 3
/ /
5 0
9 9
0 0
e A
4 7
8 3
8 1
1 E
v T
l S
S 7
7 7
7 7
v7 t
2 2
2 2
2 2
S e
Y V
A A
V V
V V
V e-S RV s
i
i;i
?.
-_.a
.i 4
s
_h h
~
q 2
6 s
1
.k 1
r 9
e 1
.s e
G R
O.-
N.-
G-N IW-ARD sev gi nt i a A
t n R
sr 4
ee c
T t l
A s
t f s ee T
i u M
l q ee RR s
tnem t e sr V
ei 0
C T uq e
R n
l o ai mt ri C
C os NoP ro t e ap 0
uy A
tTc A-ee vp A
K l y G
C aT v
)
2 4
ezn.
/
/
1 1
ii
- 1 1
S(
/eev M
vi i s A
A t s ca AP D
.yr eo C
x vae l
at
.: B x
Va.C
..A s
l e"-
i t
O an l
i 7
4 e
d u
r 0
D.
F oo B
C l
C es s
e s
i a
D l
3 3
C o.
A8 B
22
/
M:
N A
68 8
0 e
00 2
1 E
v 11 T
l VV 8
S a
CC 7
v8 Y
V LL V
e-S RV
}-r, llillj l
1t 21l'l4 i11iIj
{l l
- {
{jljil{i{^
- lj jil j
il 1
I1I i ;;
?.
T
[,
~
1 1
e e
l l
2 b
b a
a e
T T
7 t
1 1
2 o -
1 1
d d
4 s
l 1
c '
n n 1
k e e e e e a a 1
r l
l l
e d
l l
9 e
- 3 b
b b
. t n
b b
3 3
1 G
s a
a
.T Is a
o a
a a
e V
T t
T T
e e R
G 2
t t
3 0
d d
d d
1 d
d o
o V
d S
1 n n n n
V n n s
l n
V V
a a
a a
a a
- G I
I
. a O
2 3
3 1
2 1
1.
2 3
3 3
3 3
N-6 7
S.
V - G e e V
V V
S G
G G
V V
1 1
1 V
V V
V 1
e V
V V
G G-
- l l
l N
V W
W.
B I
- b W
l W
W IS b
b W W W W B
B W
I a
I u
N a
a I
I e
W W
W W
t T
N f
I I
I T
T I
I I
I IW IW W
W A
I I
N e e e. e e - e e e e e e e e e e e D
e e e e e e
.e e e e e e e e e
e S
S S
S S
S S
S S
S S
S S
S S
S k
eew gt nt J
J J
T I T I J
J J
J J i e TR t t W
AT 4T
.t n
- LR I W sr I L RLRL S
S IW T
T T
T Tt W
II I
L L
L L LI ee T t ~~
l A
e t
- f s
.V V
.f T
T T
T TV ee
- TV V VT TT TT R
t i u
- LC C CL NL NL S 4S QI L
L L
L LC g
l l q eo RI t s
tnem
.t e sr S
Si Sf T
f f
T ei C
0
- 0 Cf CI
- QN Q9 4I QN l
l t
t T ugo
. h n
l o ai
.et ri C
0 0
C C
C 0
0 C
C C
C C
9 O
0 es e
- 8 o
. - P rot e
~
ap 0
0
. 5 W
_O W
O 0
O uy A
A 9
I
.S 9
N A
A tTc A
ee vp K
K K
K L
L A
A V
V A
A A
L L
K l y C
C C
C G
G G
G R
I G
G G
G G
C t
aT v
)
e.
0 zn 0
6 6
4 4
0 t
1 i i 1
1 1
1
/
/
2 4
x x
1 3
3 5
e 6
S(
3 3
6 6
1 l
1
/eev wi ts A
A A
A A
A A
A A
A
.A A
A A
A A
t s ca
. AP D
vr eo C
x x
x x
x x
x vn i e at B
va x
x x
x C
.A x
x x
x x
m x
x x
x se r
t e
a l
n 0
l i
3 4
1 S
C. 8 0, 0 6. 3 o
d 2
- 0 3
0 3
t r
1 H.
H.
8 4
3 H.
H. F 19 8
1 1F,1 F H.
o 1
r o
N F
F 0
L L
LN L DD 1 D
D 0D HD H F
1 a
c e
l s
c s
u a
t s
l 3
1 1
2 1
1 1
1 1
1 1
1 1
1 1
2 C
L B
D 0
8 0
S B
/
D D
0 E
/
/
/
A 4
5 4A A A
4 A
A 0
1 A
A8 8 0
M e
17 6 8
7 9
0 3
4 7
T D
4 7
G 67 4 1
E v
- 2 9 2
3 3
4 5
5 7
7 P
82 9 T
l 2 -
2 2
A S
a R2 2 2
2 2
2 2
2 V
V 1
2 2
2 22 2 vs Y
V SV V V
V V
V V
V S
R S
V V_
V VV V e-S RV
- L _
l!lll
- li l'j i!l
..> J 4
,j
- l
_ f_,]>_.
76 s
1 k
1 r
9 e
1 s
e-
[
G R -
_, s o
s 4
4 d
h l
1 1
i V
y V
v G
R s
S S
s I
R R
R A
W R
R R
R AR e e e e D
e e
e e s s S
s sev gi nt i a R
R R
R t n R
R R
R sr ee Tt l
A s
t f :
e V
V V
V i ;
C C
C C
l ;
e :
R?
s
.tnem t e sr T
T T
T ei L
L L
L T uq
- e R '
n l o ai mt ri 0
0 0
0 os NoP ro t e ap uy tT c
A ee C
C C
C vp F
F F
F l y E
E E
E eT V
)
e.
zn ii 1
1 1
1 S(
/eev vi is' A
A A
A t s co AP 0
v d
r e
eo C
x a
m x
u vn n
l e i
et B
t Ve n
C o
A x
m m
m c
(
se r
t e
a l
n l
i o
d 3
3 2
s r
1 1
1 3
o r
o J
K F
M a
C e
l s
c s
u a
N l
2 2
2 2
C D
D H
8 o
/
M:
N A
A A
A 5
0 e
2 4
3 0
1 E
v 6
6 7
3 T
l 0
S e
2 2
2 2
v1 Y
V V
V V
V e-S RV
~ l_ 4 j i i"
._ ~[2
.~
'; ~'
1 e
l ba Y
8 1
d 2
m.
6 s
n 1
k e
a e
1 r
l l
9 a
, b 3
b 1
m a
V a
e T
G T
G R
d S
d n
R n
t.
a R
O 3
5.
a S
1 6
7 M
V 1
I 1
1 G
V V
e V
V G
l H
S B
S b
S S
1 R
R R
a R
R N
R R
R T
R R
AR e e e e e e
O e e e e e e
S S
S S
S S
sev gi nt i a J
J R
t n T
T
+
R sr L
L ee Tt l
A s
t f s T
T T
V V
ee L
L L
C C
i u l q ee RR s
.tnem t e V
T
.T S
T T
T sr C qM QM C QM L QM ei T uqe R
n l o ai mt C
O C
C C
0 0
C rios NoP ro t e O
0 O
D ap M
M M
M uy tT
-cA ee C
vp K
A A
K L
F A
K l y C
G G
C G
E G
C aT V
)
e.
t n
.ii B
8 8
8 8
1 3
1 S(
/eev vi is A
A A
A A
A A
A t s
.ca AP
' D yr eo C
x x
x x
vz l e at B
m x
VaC A
x x
x x
sa s
t e
s t
5 v
a 1
S id 1
- 2 1
n 0
9 8
6 1
T v
- a r
1 G.
G.
G.
F.
F.
1 1
r o
- 4
- 4 o
o 11 C
C D
E E E1 1
S C
e s
r s
o a
C l
2 2
2 2
2 2
2 2
C 8
B B
8 8
B B
.o
/
/
/
/
/
/
8
/
M:
N 4
A A
A A
A
/
A 0
1 2
3 6
1 A
3 0
e 1
1 1
1 2
3 5
3 1
E v
T l
4 4
4 4
4 4
4 4
1 S
a 1
1 1
1 1
I 1
1 v1 Y
v V
V V
V V
V V
V e-S RV l
I llIllll.
I
9.
1 1
1 6
s
~
1 9
a le le 1
k 1
r e
b b
t 1
m a
a o
e T
T N
!a G
R d
d d
n n
n a
a a
O 1
3 3
2 1
1 3
3 t
2 N
V V
V V
i e
G G
e e
e G
G V
e G
l l
l l
l N
b B
S b
b b
B S
S b
I a
R R
a a
a R
R R
t W
T R
R T
T T
N R
R T
AR e
e e
e e
e e
e e e
D e
e e
e e
e e
e e
e S
S S
S S
S S
S S
S se v
gin t
J J
J J
i a
T T
T T
R t
n L
L L
L R
s r e e T
t l
A s
t f
s e e T
T T
T V
i u
L L
L L
C l
q e e R R s
tnem t
e s r T
T T
T S
T T
T T
T V
V T
S e i Q MQMQM0M C 0MQM 0MQM QM C
C L
C T
uqe R
no l i am t C
O O
O C
C O
C C
C C
C C
C r i o s N oP rot e a p O
O O
O D
O D
D 0
u y M
M M
M M
M M
M M
t T c
A ee
~
C vp A
A A
A K
A A
L A
A K
K F
K l y G
G G
G C
G G
G G
G C
C E
C aT V
~
)
e t n.
0 0
0 4
4 4
4 0
6 6
0 0
6 ii 1
1 1
1 1
1 1
1 1
1 2
2 1
1 S(
/eev vi i s A
A A
A A
A A
A A
A A
A A
A t s n
ca o
AP i
tc D
e y
i r
n eo C
x x
x x
x i
vg l e t
at B
x x
x x
x x
x n
Va a
C l
A x
x x
x x
oo s
C e
t e
a r
n u
i 5
s d
6 1
1 s
r 1
5 7
1 6
6 7
7 1
5 4
4 G.
7 e
o r
o H
E E
D H
H H
F G
N K
K F
N P
C h
s ia sa H
l 2
1 1
2 2
2 2
2 2
2 2
2 2
2 C
D o.
2 1
A M:
N 7
4 5
6 7
8 9
0 1
7 8
5 3
3 1
0 e
1 1
1 1
1 1
2 2
5 5
6 2
6 1
E v
3 T
l 3
3 3
3 3
3 3
3 3
3 3
C 2
3
. 2 S
a 2
2 2
2 2
2 2
2 2
2 2
S L
2 v1 Y
V V
V V
V V
V V
V V
V V
S S
V e-S RV l.
J
\\l i]
j r
w 1
t.
h S
96 s
1 k
1 r
9 a
1 m
e G
R
+
0 1
3 3
3 3
0 V
V V
V 1
e G
G G
G G
.l e s B
N b
8 I
a R
R n
R d
.T R
R a
R lAR c.
D
. e e e e e
e e e e e
S S
S S
S sev
'g i
~
nt J
J J
J i a T
T T
T 9
7 t n
+
L L
L L
sr ee tt l
A
~
~
s t
f s
~
ee T
T T
T i u L
L L
L q
lee RR s
t n
em t e sr V
T V
V V
V ei C QM C
C C
C T uqe
. R n
l o ai mt ri C
C C'
C C
C os No
- P ro' t e ap O
uy A
M tTc A
ee vp K
L' K
K E
E l y C
G C
C C
C aT v
)
)
d e.
e t n 4
4 2
2 3
3 u
ii 1
n S(
i tn
/e o
ev c
~
vi
(
is A
A A
A a
A t s n
ca o
AP i
tc D
e y
j r
n eo C
x x
x x
u I
vg l e t
at B
x n
Va a
l
- C A
x x
x x
oo s
. C e
t e
an r
i us d
1 s
r 1
9 5
3 3
e o
r o
F G
E K
J J
P C
h s
ig s
a H
l 2
2 2
2 2
2 C
o.
3 1
N 2
3 2
5 6
3 4
4 0
M:
e 3
2 5
2 8
8 1
E v
T l
3 3
3 C
3 3
. 3 S'
a 2
2 2
S 2
2 v1 Y
V V
V V
S V
V e-
. S RV
[I f
!f
59 i.
ii Ill1I i:
- )9 t
,7,5
~-E W,h 2
.t 5, S.
R.9
. 6 s
1 k
1 r
9 e
- 1 m
o
.N R
i.
D 9
N 1
V S
N S
l A
le R
u N
ee I
S s
ev gi nt ia t n sr ee Tt l
A s
- t f ;
M e
T M
i leRC s
t
.ne
- m t e sr T
T V
V T
T ei OQM QM C
CQMQM T uqeR n
l o ai mt_
ri
'C C
C C
C C
C os NoP ro t e ap 0
O O
O 0
uy A
H H
A A
tT c
A' ee vp A
A L
K K
A A
iy G'
G G
C C
G G
a T.
V i ).
rn 0
0 i i 2
1 1
2 2
1 1
S(
/eev vi is A
A A
A A
A A
t s n
ca o
AP i
t
. c
.D
. e
- y i
r n
eo
.C x
x i
vz 1, e t
It B
x x
x x
x n
Va a
C i
A loo s
C e-t o
a r
n u
i s
d 0
4
- 4 0
0 1
1 s
r-1 1
1 1
1 1
1 e
o r
o J
E E
L L
M M
P C
h s
g s-i a
H l
2
.- 2
- 2 3
3 3
3 C
o 9
0 N
Ae el 0
1 3
4 0n no 3
3 0
M e.
5i i r 1
1 3
3 1
E v
bpbt 2
2 T
l-3 rorn 3
3 V
V
. 4 e:
2 ut uo 2
2 C
C v1 M
i}
i!
[
t 7 V-
.VTST C V
V L
L e-
m lq;jij
)
li f'i.
y6 i
f 2
L p
u y
- f.%
5,
[
- 0 1
2 3
7 s
2 V
1 k
Y e
G 1
r~
l
.9 e
S b
B 1
s R
a R
e R
T R
G R'
d d
d n
n n
a a
a s.
,O O
0 0
0 3
2 2
3 3
N 2
2 2
2 V
2 1
V V
V V
V V
G V
G G
_G e
N B
B B
B B
B t
S B
I
.R R
R R
R R
o R
R
~AW R
M M
R R
R N
R R
e R
e e
e.e e
e e
e e
,..D e
e e
e e
e e
e S
S S
S S
S S
S S
sev gi nt J
J J
J
. i a R
R
.R T
T T
T
. t n R
R R
L L
L L
sr ee Tt ~
l
. A s
t
.. f y e E~
V V
T T
T V
V V
i J C
C QMqM L
C C
C l q e
.Rt s
.tn
. em
,t e
sr T
T S
V ei
- QM QM C
C
.- T uqe
. R n
l o ei mt ri
,C C
C C
0 0
O C
O 0
0 os NoP r
_ o t e
. ap 0
0 0
0
. uy' A
A A
A
,tTc A
.ee vp K
K A
A A
A K
K K
K K
l y C
C G
G G
G C
C C
C C
aT
.V
)
2 e.
/
t n
. 4 2
4 1
2 4
4 ii
/
/
1
/
1 2
1
/
/
/
S(
3 1
3 2
1 3
3
./e ev vi i s A
A A
A A
A A
A A
A A
t s ca
.AP
.s c
0 t
i y
i l
r n
u eo C
x x
x x
x x
x U
a vae l
r l
d at
.B x
x x
x o
y Va r
H C
t A
x x
x x
n e
o v
s C
i e
r t
c D
a i
n l
d u
i o
d 8
6 6
8 1
6 2
2 a
R r
1 1
1 12 6
21 1
1 1
r o
0 0
d l
o C
B C
CB1 D
JB1 B.
E E
y o
C H
r t
s 9
n s
8 o
a C
l 2
2 2
2 2
2 3
3 2
2 2
r C
o f
4 5
E 7
E 0
8 1
1 2
2
/
B 3
B B
l o
1 1
1 1
A A
/
1
/
/
a N
2 3
A A
A c
3 3
3 3
3 3
1 2
3 2
3 i
0 M
'e 1
1 1
1 8
6 1
1 1
p 1
E v
3 3
1 1
4 4
y DE W DCWC 3
3 V
3 T
5 l
TE a
3 3
9 7
7 X
73 73
?
U0 7
(
1j1 lll 1I 1
1 i
ld y
s
^
~
1 0
0 7
s 1
1 9
1
. k 1
r e
e e
7 e
t t
t 1
m o
o o
e N
N N
G R
d d
d n
n n
r.
a a
a O
3 3
4 N
4 2
2 2
V V
V G
e N_
t B
S S
o R
R R
l W
N R
R R
AR e
e e
e D
e e e e
S S
S S
sev gi nt i a T
t n G
sr ee Tt l
A s
t f s V
ee V
V R
i u C
C S
l q ee RR s
tnem t e sr T
T T
V ei D
L L
C u
T. qe R
n l o a
J-mt ri C
C C
C C
os NoP ro t e ap tT X
uy P
c E
A ee vp A
K K
K V
l y G
C C
C R
aT V
l-
)
2 2
2 2
/
/
/
/
et n 1
1 1
1 2
ii X
S(
1 1
1 1
I
/eev vi is A
A A
A A
t s ca AP me t
D x
s y
y r
S eo C
x x
x X
vg l
l e o
at B
r Va t
C n
A x
x o
C se d
t i
a u
n q
d 7
8 i
id L
r H.
3 2
J.
K, o
y o
G H
H h
G b
C dn s
a s
t a
S l
2 1
1 2
2 C
B B
o
/
/
B N
A A
/
4 6
7 3
A 0
M:
e 1
1 1
4 9
1 E
v 3
T l
1 1
1 1
6 a
1 1
1 1
R v1 M
V S
V V
V S
t 9 '
LiII' L
e-L
d 2
n d
1 1
1 1
1 1
1 1
2 7
s a
n 1
k a
e e
e e
e 9
a 2
b b
b b
l le e
e e
1 r
1 l
l l
l l
l l
b b
b b
b 1
m e
a a
a a
a a
a a
a e
7 e
T T
T T
T T
T T
l G
R t
lb d
d d
d d
d d
d d
a T
a n
n n
n n
n n
n n O.
T.
a a
a a
a a
a a
a 5
1 1
3 5
3 3
3 3
3 3
5 1
M 2
V 2
V V
V V
V V
2 V
e e
G l
l G
V G
G G
G G
G V
e l
N B
b b
B e
B S
B 8
B S
8 b
I R
a a
R R
R R
R R
R R
R a
W R
T T
R R
R R
R R
R R
R T
AR e
e e e e
e e
e e
e e
e e
D e
e e
e e
e e
e e
e e
e e
S S
S S
S S
S S
S s
S, S
S
=
4 sev gi nt J
J J
J J
J J
i a T
T T
T T
T T
t n L
L L
L L
L L
sr ee T t l
A s
t f s iee 1
T T
T T
T T
T T
T u
1 L
L L
L L
L L
L L
l q ee RR s
tn T
e L
m t e sr S T ST T
T T
T T
T T
S V
T ei C M CM QMQM QMQ M
- QMQMQM C
CQM T uqe R
no l i ae t r i C
C 0
C C
C C
C C
C C
C C
C o s N oP rot e
.0 O
0 0
0 0
D O
a p 0
0 G
0 u y M
M M
M M
M M
M M
M M
M t T c
A ee vp A
A A
A L
A A
A L
L A
K K
A l y G
G G
G G
G G
G G
G G
C C
G aT V
e )
izn.
0 0
4 2
4 2
0 2
4 6
i 2
2 2
1 2
1 4
4 1
4 1
2 1
4 S(
/eev vi is A
A A
A A
A P
P A
A A
A A
A t s ca AP D
y r
eo C
x x
v o l' l e l
at 8
x a
Va x
v C
o A
x x
x x
m x
x x
x x
x me s
R e
t t
a a
n e
i 33 H
d 11 3
r 8
86 T
l o
2 - 1 te 8
9 84 4
4 7
44 1 0 4 4 = 1 - -
a o
G FE1 C1 D1 C1 C
8E1 E1 D1 E1 LJ H
u C
d is ss e
a R
l 1
1 1
2 1
2 1
1 2
2 2
1 2
0 C
B B
B B
B B
B B
D o
/ / / /
/ / / / -
M:
N A
A A
A A
A A
A A
7 8
5 6
7 1
2 3
4 8
9 6
8 7
0 e
1 1
2 2
2 3
3 3
3 3
3 4
4 5
1 E
v T
l C
0 0
0 0
0 0
0 0
0 0
0 3V 0
. 7 S
a I
1 1
1 1_
1 1
1 1
1 1
1 1
v1 Y
V V
V V
V V
V V
V V
V V
V e -
S RV i!
,{
tll
1
,I 1-iI
,I l
1i
,I1 l1!!;
i 2
7 s
5 1
k 1
r e
9 a
t 1
m o
e M
[
G R
dn O.
a 1
6 3
3 1
1 7
M 2
V V
2 e
V G
G e e V
G l
l l
N b
B S
S b
b 8
I a
R R
A a
a R
W T
R R
N T
T R
AR e e e e e e e D
e e
e e e e e
S S
S S
S S
S sev gi nt J
J i a T
T t n L
L sr ee Tt l
A s
t f s ee T
T T
V i u M
L L
C l q ee RR s
tne
. m t e sr T
T T
V T
T ei QM QM 0 QM C QM QM Tu qe R
n l o ai nt ri O
C C
C C
O C
C os MoP rot e ap O
0 D
0 O
0 uy M
M M
M M
M tT c
A ee vp L
A L
A K
A A
E l y G
G G
G C
G G
C aT V
)
I e.
zn 0
2 0
0 ii 2
4 1
4 3
2 2
1 S(
/eev vi 1
is A
A A
A A
A A
A d
t s e
co u
AP n
i t
C n
y o
r c
eo C
x x
(
va l e l
at 8
x x
x x
m a
Va v
C o
A x
x me s
R e
.t t
. n 11 11 1
a 00 00 4
se 5
H id 5
3 7
r 31 1
11 6
6 88 88 3
l o
ML I1 J JL JK J
- 2 a
o JE H
u C
d i
s s
s e
a R
l 2
2 3
2 2
2 2
2 C
B 8
8 D
.D D
8 o
/
/
/
/
M:
N A
A A
A A
A A
5 6
9 6
9 3
5 6
0 e
6 6
8 1
1 1
1 3
1 E
v T
l 0
0 0
0 0
0 0
0
. s S
a 1
1 1
1 1
1 1
1 vI Y
V V
V
. V V
V V
V V
e-S RV Il[I l!lll!Ill[lllliIlll{llIl llIll l
l l
l'
!l,'
i
!ll
!1 l
ll!!L
4.
1 1
1 T
s 1
e e
1 k
l l
e 1
r 9
a b
b t
1 m
a a
o
~
e T
T M
G R
d d
d n
n n
a a
a O
3 3
2 1
1 3
3 8
3 N
V V
V V
2 V
G G
e e
e G
G V
G G
l l
N 8
8 b
lb b
S 8
8 S
7 R
R a
a a
R R
R R
M R
R T
T T
R R
R R
A R
e e
e e
e e
e e
e D
e e
e e
e e
e e
e S
S S
S S
S S
S S
sev gi n t J
J J
J J
i a T
T T
T R
T t n L
L L
L R
L s r e e T lt A
s t
f s e e T
T T
T V
T i u L
L L
L C
L l qe e RR s
tnem t e sr T
T T
T T
S T
T T
V V
T T
V ei QM QMQMQM QM C0M QMQM C
C L
0M C
T uqe R
n l o ai mt ri O
O O
O C
C C
C C
C C
0 C
C os N oP ro t e O
O O
O 0
0 0
D D
ap M
M M
M H
M M
M M
uy t T c
A ee C
vp A
A A
A A
K L
A A
K K
F L
K l y G
G G
G G
C G
G G
C C
E G
C aT V
e )
zn.
i i 3
3 6
4 4
4 4
6 6
8 8
1 2
6 S(
/eev vi i s A
A A
A A
A A
A A
A A
A A
A t s ca a
AP n
i l
D o
v o
r C
eo C
x x
x x
x va n
e o
lat 8
x x
x x
x m
i V a t
C a
A x
x x
m x
x lo s
s e
I ta e
n ro i
d 4
0 0
3 0
1 4
C r
7 9
1 1
9 9
1 1
1 T
7 8
1 1
o r
o 0
0 E
G G
G E
F N
K K
B 1
E o
C tc s
a s
e a
R l
1 1
2 2
2 2
2 2
2 2
2 2
2 2
C 0
o A
M:
M 9
5 5
6 8
0 1
2 0
9 1
0 5
7 9
0 e
1 1
1 2
2 2
3 3
4 5
3 2
1 1
E v
1 3
T l
3 3
3 3
3 3
3 3
3 3
C 1
3 3
. 9 S
a 1
1 1
1 1
1 1
1 1
1 S
L 1
1 v1 Y
V V
V V
V V
V V
V V
V S
S V
V e-S RV l
I l.
I
_..t.~!l(i
!I
,4 z.
'(_.
. o.
g' y'
~1 t
h S
4 7
s 1
k 1
r 9
e 1
s e
f G
R O
2 3
3. 3 N
V V
V e
G G
G S
l N.
b S
S S
a R
A R
1 fn T
R R
II AR e e e e O
e e
e e S
S S - S s
ev gi
. nt J
J J
i a T
T T
t n L
L L
sr ee Tt l
A s
t f s ee T
T T
iu L
L L
l q ee RR s
tnem t e sr S
V V
V ei C
C C
C
. T uqe R
n l o ai mt ri C
C C
C os NoP ro t e ap uy tT c
A ee vp K
K K
K l y C
C C
C aT v
)
)
e.
d.
ii 6
2 2
2 zn eu S(
n i
t
/ e n
ev o
vi c
. i s A
A A
A
(
t s ca a
AP n
i l
D o
y o
r C
eo
'C x
x x
x va n
l e o
at B
i Va t
.C a
A x
x x
lo g
s e
I ta e
n r
i o
d 1
1 1
C r
1 1
1 9
o r
o N
J K
K o
C tc s
a
. s e
a R
l 2
2 2
2 C
o 0
N:
N 1
0 9
0 0
e 4
2 3
3 1
E v
1 TS -
l 3
3 3
C 0
a 1
1 1
S v2 Y
V V
V V
S S
e-RV
~
e!llfLi(ill i}
\\;11jij ii l1 1
l
~
2 t'.
hS 4
7 s
1 k
1 r
9 a
1 m
e G
.R 0
9 0
0 8
2 3
3 V
V V
G.
N S
S S
I R
R R
de R
R R
aR e e e D
e e
e S
S S
s
.ev gi nt ia R
R t n R
R sr
. ee Tt l
A s
t
. f s ee T
V V
. i u M
C C
l q ee RR e
tnem t e sr T
T T
T ei QM 0M 0
- QM qP T uqe R
n l o ai mt ri C
C 0
C C
C C
os NoP ro t e ap 0
D D
0 O
uy M
M H
A A
tT c
A ee vp L
L L
K K
A A
l y G
G G
C C
G G
aT V
)
e.
rn ii 3
2 2
2 2
1 1
S(
./eev vi is A
A A
A A
A A
t s co e
AP n
i l
.D o
y o
r C
eo C
x x
va n
i e o
at 8
x x
x x
x i
Va t
C a
A lo s
s e
I ta
' e n
r i
o d
5 2
3 0
0 0
C r
1 T
1 1
1 1
1 o
r o
D G
D K
K M
09 o
C tc s
a s
e a
R l
2 2
2 3
2 3
3 C
.o v
2 3
N 1
2 o
3 1
1 M:
e 1
1 G.
0 3
0 3
3 T
1 3
3 1
E v
b 1
1 T
l 3
3 r
3 3
v V
.1 S
a 1
1 u
1 1
C C
v2 Y
V V
V T
V V
L L
e-S RV L
f il!llliIIll
!lli I,
llf<
b b
5 1
1 1
a 1
1 2
a 1
7 s
e e
T T
1 k
t l
e e e
e e
e e
1 r
o b
l l
9 a
N a
b b
lb 6.
l l
l l
b b
b 6
b 1
m T
a a
a a
a a
a e
T T
T e
T T
T e
T
+
G R
2.
d t
t 3
n d
d d
o d.
d d
o d
V a
n n
n N
r n
n N
n a
a a
's.
3 3
3 3
3.
a a
a a
O 1
3 3
3 3
3 3
3 3
3 N
3 V
V V
V V
V V
V V
V V
V V
V V
G G
G G
G G
G G
G G
G G
G G
G N
8 S
B B
B B
B 8
B S
S B
S S
B I
R R
R R
R R
R R
R R
R R
R R
R W
R R
R R
R R
R R
R R
R R
R R
R AR e
e e e e
e e e
e e e e e
e e
D e
e e
e e
e e
e e
e e
e e
e e
S S
S S
S S
S S
S S
S S
S S
S sev gi nt J
J J
J J
J J
J J
J J
J J
J i a S
T T
T T
T T
T T
T T
T T
T T
t n CL L
L L
L L
L L
L L
L L
L L
L sr ee T t l
A s
t f s ee V T T
T T
T T
T T
T T
T T
T T
T i u C L L
L L
L L
L L
L L
L L
L L
L l q ee R R s
tnem t e s r T
- S T
T S
T ST T
T e i
- QM
- C M
- QM CQM
- CMQMQM T uqe R
n l o am i t
r i C
0 C
C C
C C
C C
C O
C 0
0 O
o s N oP ro t e a p 0
0 0
0 0
0 0
0 O
O 0
0 O
u y A
A A
A A
A A
A S
S A
A S
t T c
A e e v p K
F F
F F
F F
F F
K A
A F
F A
l y C
8 B
B 8
S 8
8 S
C G
G 8
B G
a T V
)
e l
zn.
o 8
8 8
8 8
8 0
0 r
ii 1
8 3
1 1
1 1
1 2
2 1
1 6
3 1
t S(
no C
/e ev e
vi r
i s A
A P
P P
A P
P A
A A
P A
A A
e t s h
ca p
AP s
o m
D t
y A
r eo C
x va x
d lat B
n e
a Va t
C n
A x
x x
x x
x x
x x
x x
x x
x x
e m
s n
e i
t a
a n
t 5
6 n
o di 2
1 1
2 6
3 2
2 6
2 C
r 8
2 2
1 k.
M.
M.
1 1
1 1
1 1
2 1
o y
o J
0 F
D E
I I
J K
K G
H G
L H
r C
a m
s i
s r
a P
l 2
2 2
2 2
2 2
2 2
2 2
2 2
2 2
C A
0 A
8 o
6 6
7 8
9 1
0 2
2 2
2 2
M:
N 9
9 99 9
9 99 3 9 9
1 1
31 1
1 1 1 9
0 0
21 0
0 e
1
- - 81 8 2
2 2
1 E
v
- J 6
6 66S 6
6 66/ - /
96 T
l 6 -
1 1
[1 /
1 1
A6A 6
6 1 1 6
2 1_1 S
a 1 A 0
8 88A 8
8 8
1 2 1
1 888 1
v2 S_8 1 Y
V VS S
5 S5T S
S 51 V1 V
V S56 V
e-S RV
i!
il11lIi1Iii I
- 5~O~
t+'
4 I
-w
.~
t 1
t h
7 S
. 's 5
7 1
.k 1
r 9
a 1
m
'G
. e R
o 3
3 N
V V
G G
G N
S B
l R
R f
R R
lA R
e e
D e
e S
S se
_v gi nt J
J i a T
T t n L
L sr ee T t l
A s
t
- f s ee V
V i u C
C l q ee RR s
tne
.m t e sr ei T uqe R
n
- l o ai mt ri C
C os NoP rot e ap uy
)'
t T d
c-e A
un ee i
t vp K
K n
l y C
C o
aT C
V
(
)
l e.
o t n r
ii 2
2 t
S(
no C
/ e ev e
vi r
. is A
A c
.t s
h ca r
AP v
D t
. v A
r eo C
x x
d va n
l e a
et B
Va t
.C n
A x
x em s
n e
i t
a a
t n
n i
o d
1 1
C r'
1 1
o
+
y o
J J
r C
am s
i s
r a
P l
C C
C 1
2 o
5 5
N:
N 9
9 0
e 1
1 1
E v
T l
6 6
3 S
a 1
1 v2 Y
V V
V e-S RV tI!l!Ill ll!l(tllII
,1]-IIji
- I
'lli
~
1 t
hS 7
7 s.
1 1
1 1
1 k
e e e e 1
r l
l l
l 9
e b
b b
b 1
s a
a a
a e
T T
T T
G R
d d
d d
n n n n a
a a
a O
3 3
3 3
N V
.V V
V G
G
.G G
G
.S 8
N s
S I
t W
.u R
S R
A l
R - R R
R e e e e D
e e e e S
S S
S s
4 ev gi nt J
J J
J
. i a T 7 T T
T t n L
L L
L sr ee T t
.lA s
t f s ee T
T T
T iu
- L L
L L
l q ee
. RR s
tne
.m t e sr T
T T
T ei QM QM QM QM T uq
- e
- R n
l o ai mt ri 0
O O
O os No P
rot e ap 0
O O
O uy A
A A
A
. tT c
A ee vp A
A A
A l y G
G G
G aT V
)
e zn i i 3
3 3
3 S(
. / e ev vi is A
A A
A t s ca AP D
. vr eo C
va l e at
.B VaC A
x x
x x
s e
e e
_t t
_ a s
n w
i S
dr 4
5 4
5 e
..o t
o 8
8 G
G s
C e
s e
e s
e o
R l
2 2
2 2
C
.o M:
N 2
3 4
5 0
e e
8 9
9 E
v 1
T l
0 0
0 0
S a
2 2
2 2
4 v2 Y
v V
V V
V S
e-RV m
,I!!;Ll l'
,]
l
~
Ii
+
.^
z t
~
u.:
1 t
hS l'
8 1
7 s
k k
e e
a-:
1 r
.l l
9 a
b b
1 m
a a
e T
T G
.R d
d n
n a
a O
3 3
3 3
N V
V V
3 G
C G
V G
M B
B 8
S I
R R
R R
W
.R t
R M
i AR
'e e e e D
e e e e
S S
S S
s
. ev gi nt J
J J
i a T
T T
R t n L
L L
R sr ee Tt l
. A s
. t f s
. T V
ee T
T i u l q
- L L
L C
ee RR s
tn
. e m
t e sr T
T T
~-
ei QM QM QM T uqe R
n l o ai et ri O
O O
O os MoP rot e ap O
O O
uy M
M M
tTc A
ee
.vp A
A A
K l y G
G G
C aT V
)
ezn.
.ii 4
4 4
3 S(
./eev vi is A
A A
A t s ca AP me D
t y
s r
y eo C
x S
va l e
~
p at B
u va n
C a
A x
x x
e l
s C
.e t
r a
e n
t i
a d
1 W
. o r
2 3
1 17 r
o D
D L FD o
C tc s
a s
e a
R l
1 1
3 3
C B
.o
/
N A
5 8
8 8
0 M
e 1
1 6
2 1
E v
T
.i 2
2 2
2 5
S a
1 1
1 1
v2 Y
V V
V V
V e-S e
RV il!t!IlIliI lll[l
Q, iq
..u 1
IJl 4
111]
7
~
1 f
2_
7 3
s 2
._k 1
r 9
.a 1
m e
G R~
O.
4 N.
3V G
N.
S I
R W
R A_
R.
e D-e S
_ se v
. gi nt i a t n sr
. ee
.Tt l
A s
t
. f s ee V
.i u C
l q ee RR s
tn em
. t e sr V
. ei C
u
- T. qe
.. R n
. l o'
. ai
. mt
. ri 0
C os NoP ro e ta p' uy
. tT c
. A ee vp K
K
.l y-C C
aT V
)
e
. zn-4 ii 3
/
S(
3
./ e ev
. vi
. i s-A A
s tca' AP' y ~ D e
r i
va
- C x
x n
eo e
l l
o at
. B o
Va C
C A
~
CA s
V e
H tan
~
m i
oo d
1 1
R r
1 1
o l
o J
J o
C r
2 s
n s
o a
C l
3 3
C
.o N
A A
5 0
N e
8 6
1 E
v T
l W
W 6
S a
C C
v2 Y
V.
S S
e-l
- i
)
l!
l3 B-
8 3
s 2
k 1
r c.
9 e
1 m
a G
n O.
1 1
1 l
1 1
1 1
1 N
e e e e
'e e e e e
S l
l l
l l
l l
l l
N b
b b
b b
b b
b b
I a
a a
a a
a a
a a
N T
T T
T T
T T
T T
A t
f e e e e e e e e e
O e
e e
e e e e
e e
S S
S S
S S
S S
S
~
se
. w gt n t i a t n s r e e T t l
A s
t f s E
e e i u l q le e f R s
tn em t e
~
s r T
T - T T
T - T
' T T
T e i QN0MQNQN OM0N QNQM QM T u q
en
.fn l
o C'
C a
i m
t
/ /
C 0
0 C
C 0
0 0'
0 r
i o s N
o P
ro t
e a p 0
O 0
0 0
0 0
0 0
u y
A A
A A
A A
A A
A t
T c
A ee vp F
F F
F F
F F
F F
l y S
B S
S S
S B
B O
aT
~
V -
)
e.rn.
2 2
2 2
.4 6
5 5
4 4
4 4
i i 1
1 1
1 S(
/eev vi
.is A
A A
A A
A A
A A
t s ca AP D
vr
- e. o C
g n
n i
ie et B
x x
m x
u m
m x
m d
ve l
C A
iu G
se r
t o
a t
n ca i
d e
r 9
T 7
7 T
9 9
9 9
R o
o I
I G
1 H
J J
H H
C C
e A
s W
a H
l 2
2 2
2 2
2 2
2 2
C o.
S
'8 S
B N:
N
/ / / /
0 1
2 A
A A
A 9
1 1
1 0
e 1
2 3
4 5
1 E
v C
C C
C T
l T
T T
T T
A A
A A
.T S
a G
G G
G G
W V
V V
v2 Y
V S
S S
S S
H H
H_
H e-S RV l'
7 6
s 2
k 1
r 9
a 1
m e
G R
O.
5 5
5 - 5 5
5 5
5 5
5 5
5 5
N 3
3 3
3 3
3 3
3 3
3 3
3 3
V V
V V
V V
V V
V G
V V
V V
N 8
8 S
8 8
B S
B S
e e S
8 I
R A
R R
R R
R R
R R
R R
R W
R R
R R
R R
R R
R R
R R
R A
R e
e e e e e e e e e e
e e D
e e
e e
e e
e e
e e
e e
e S
S S
S S
S S
S S
S S
S S
sev gi n
t i
a R
R R
R R
R R
R R
R R
R R
t n
R R
R R
R R
R R
R R
R R
R s r e e t
t l
A s
t f
s i
e V
V V
V V
V V
V V
V V
V V
e u C
C C
C C
C C
C C
C C
C C
l q
e e R
R s
tnem t
e s
i T
T T
T T
T T
T T
T T
T T
r e
L L
L L
L L
L L
L L
L L
L T
uqe R
n l
o am i
t o
i 0
0 0
0 0
0 0
0 0
0 0
0 0
r s N o P
ro t
e ap uy t T c
A ee C
C C
C C
C C
C C
C C
C C
vp F
F F
F F
F F
F F
F F
F F
y E
E E
E E
E E
E E
E E
E E
laT V
e )
z n.
iiS(
1 1
1 1
1 1
1 1
1 1
1 1
1 no
/ e i
ev t
vi a
i s A
A A
A A
A A
A A
A A
A A
t t s n
ca e
AP mur D
t y
s r
n eo C
x x
x x
x x
x x
x x
x x
x I
va l e l
at B
e Va s
C s
A x
x x
x x
x x
x x
x x
x x
ev se r
t e
a l
n i
i o
d 2
2 B
r 4 4 4,
4 4
4 1
1 4
4 4
4 4
o
- 2 2 2 r
o 0E1 E1 F1 G1 J1 G1 I
G H
J J
I a
C e
l s
c s
u a
N l
2 2
2 2
2 2
2 2
2 2
2 2
2 C
o.
B B
B B
0 D
H 0
/ / / /
M:
N A
A A
A A
A A
1 1
3 5
7 9
1 3
5 1
1 3
5 7
0 e
1 1
1 1
1 2
2 2
3 3
3 3
2 1
E v
T l
3 3
3 3
3 3
3 3
3 3
3 3
3 8
S a
v2 Y
V 2
2 2
2 2
2 2
2 2
2 2
2 2
e-S RV a
l-
)9jY i
~
~
76 s
2 k
1 r
. 9 a
1 m
e
. G R
D 5
N 3V G
G I
B I
R
. N R
_ A R
e D
e S
sev gi nt i a R
t n R
sr ee Tt l
A e
t f s ee V
i u C
l q ee RR s
.. tnem t e sr T
ei L
1 uqe R
n l o ai mt ri 0
os NoP ro t e ap uy tT c
A ee C
)
d vp F
e l y E
u aT n
v i
t
)
n e.
o zn C
ii 1
(
S(
n o
/e i
ev t
vi a
is A
t t s n
ca e
AP m
. u r
D t
v s
r n
eo C
n
- i vn l e l
at B
e va s
C s
A x
e V
s e
r t
e a
- i in~
2 l
o d
1 B
r 4
o r
o G
a C
e l
s c
s u
a
- N l
2 C
S o
/
h A
9 N
e 2
0 E
v 1
T l
3 S
a 9
Y V
2 v2 S
e-RV iI i.
l!
e e e t
t t
o o
o 2
N N
N 00 d
d d
1 n
n n
1 1
1 1
1
'l 1
1 1
5 s
a a
a T
k e
e e e e
e e
e e
e r
1 1
1 l
l l
l l
l l
l E
a lb b
b b
b lb b
b b
b m
a e
e e
a a
a a
a a
a a
a Y
e T
l l
l T
T T
T T
T T
T T
V R
b b
b d
a a
a d
d d
d d
d d
d d
n T
T l
n n
n n
n n
n n
n a
a a
a a
a a
a a
a O
3 3.
3.
3 3
3 3
3 3
3 3
3 3
3 N
V V
V V
V V
V V
V V
V V
V V
G G
G G
G G
G G
G G
G G
G G
G N
S B
B B
S S
B B
S S
S S
S 8
I R
R R
R R
R R
R R
R R
R R
R N
R R
R R
R R
R R
R R
R R
R R
A R
e e
e e e
e e e e
e e e e
e D
e e
e e
e e
e e
e e
e e
e e
S S
S S
S S
S S
S S
S S
S S
sev gi n t J
J J
J J
J J
J J
J J
J J
J i a A T ATA TAT AT AT ATAT ATATAT AT AT T
t n R L RLR LRL RL RL RLRL RL RLRL RLRL L
s r e e T
t l
A s
t f
s i
e T
TTTT TTY T T T T TTTT TTTTTT TTTT T
e u M LMLM LML MLML ML ML MLML ML NLML L
l q
e e R R s
tnem t
e e ir s
T 0
O O
O O
0 O
O O
O O
O 0QM T
uqe R
n l
o a
i m
t o
i C
O O
O O
C O
O O
O O
O C
C r s N
o P
ro t
e a p O
O O
O O
O O
O O
O O
O O
0 u
y S
S S
S S
S S
S S
S S
S S
M t
T c
A ee vp A
A A
A A
L L
L L
L L
L L
L y
G G
G G
G G
G G
G G
G G
G G
laT V
e )
zn iS(
i 1
1 1
1 1
1 1
1 1
1 1
1 1
1
/eev vi is A
A A
A A
A A
A A
A A
A A
A t s n
ca io AP tu D
l y
i r
D eo C
e lvme r
at B
e Va h
C p
A x
x x
x x
x x
x x
x x
x x
x so s
g m
e t
t A
an t
i n
d 4
2 2
2 4
4 9
1 1
9 1
1 2
6 e
r 1
1 1
1 1
1 1
1 1
1 1
1 1
1 m
o n
o J
I G
G L
J J
L L
J L
L G
8 i
C a
t s
n s
o a
C l
2 2
2 2
2 2
2 2
2 2
2 2
2 2
C 5
5 5
5 E
4 o.
7 T
7 7
T e
3 B
M:
N 9
9 9
9 9
B
/
0 0
0 0
0 A
/
A 0
e 1
1 1
1 1
5 3
4 5
6 3
4 A
2 1
E v
-O 2. O 2. O 2. O 2. O 8 7
2 2
2 2
3 3
9 2
T l
0 S
a S1 S1 S1SI S/
G G
G G
G G
G G
G v3 Y
V FAF8FCFDFA V
V V
V V
V V
V V
e-S RV
- j. jj
]
- d. s r
4 200 1
1 1
5 s-1 k
e e e r~
l t
l E
a b
b b
m a
a a
Y e
T T
T V
. R n M d
d n
a ' a a
O 3
3 3
N.
V V
V G
G G
G N-S S
S 1.
R R
A
- e R
R R
U I
e e e D
e e
e S
S S
sev gi nt J
J J
ia AT AT AT t n RL RL RL sr ee Tt
- lA s
.t f s ee TT TT TT iu ML ML ML l q i
ee RR s
.tnem t e sr ei 0
0 0
T uqe R
n l o ai mt ri C
C C
os NoP rot e ap O
O O
uy S
S S
tT c
A ee vp L
L L
l y G
G G
aT V
)
)
d e.
e zn u
i i 1
1 1
n S(
i tn
/e o
ev c
vi
(
is A
A A
t s
~
n ca o
AP i
tu D
l y
i r
D eo C
va e
l e r
at B
e va h
C p
A m
m x
so s
m e
t t
A an t
i n
d e
r 9
9 9
m o
n o
G 1
1 C
ia I.
t s
n s
o a
C l
2 2
2 C
.o B
B B
N
/
/
/
A A
A N
e 1
2 3
0 1
E v
1 1
1 T
l S
a G
G G
.1 Y
V N
N N
v3 S
e-RV l
)
l'
f 9
q j!
i I
e~ 7
- ,. 7;. '
.U tr 7
m T,
, [s s
h 2~
-:.m s'a 2
mn f
m
~
'.i h
,. L s
k
~
r e
m..
Y e
s
..w R
6 3
. V
.g; 3
.u..
.V G
r m:
S m
R H
e e
m S
e.3..
. s e
.. v
. gt.
nt
,J i e T
t n L
sr
- ee Tt
. l A
s t
f s
. T ee iu L
l q ee HR s
. tn
. em
't e sr' T
T ei qM
. D Tu'q' e'
R
- n' l o' ai' mt ri C
. O os No' P '
rot e'
. P' ap D
X uy M
. E
, tT
_ c A'
v p '-
ee
L
. G A
y' B
. l a T.
v
)
_ a.'
8 8
rn
/
/
. i i 3
3 S(
w
/ eev' vi' i s A
A
.. t s
. ce AP D
x
. y
. r eo C
vz l e at
,B VaC
.A m
se
. t
. an i
- r. d
- r o
A A
o N
N
. c s
p s
g a
h y
l 2
. 2 C
C o
C N
A A
0
- c
.._l
. e r
1
. v l
a y
l e
2 s
a a
h v3
_ y V
B S
e-
+ g ll 1
l' ll ll l
l I!
R3
\\
RELIEF REQUEST BASIS NUMBER:
V1 SYSTEM:
. VALVE:
V70-1A-D CATEGORY:
C CLASS:
3 FUNCTION:
Service Water Pump Discha'ge Check Valves r
' TEST REQUIREMENT:
CV BASIS FOR RELIEF: A review of plant operating history has shown that all (4) service water pumps are normally required for pla.it operation.
during approximately seven-(7) months of each year. This is due to system heat loads.. As such, the shutting down of a pump for check valve testing is not practical.
During the remainder of the year, three (3) of the four (4) pumps are required for plant operation. The pumps are.routi-nely rotated when possible.
ALTERNATE TESTING: Valves wil1~be exercised as pumps are rotated in service.
Proper pump operation will indicate proper opening of the check valves. Absence of pump runback or system pressure loss as noted by operations personnel will indicate proper closure of the check valves.
The testing will take place during the period when only three (3) pumps are required. The frequency of such testing will be twice per year with a minimum interval between tests of three (3) months.
l Rev. 10
-V-33 I
_a-s.--_-
--.---.___----_.__--__.__.-_.__._Y_---__.._-._-_-
_ _ _ - _ - _. - _ - _ _ _ - _ _ _ - -.. _. ~ - - - - - - - -. _.. _. _. - _ _ _. _ _ -.. _ _ _ _ - - _ -.
...-__.,._-_-----_-_-.-a
};
e-L RELIEF REQUEST BASIS
' NUMBER:.
V2
~
. SYSTEM:
' Service' Water VALVE:
V70-43 A/B CATEGORY:.
C CLASS:
3 FUNCTION:
Check Valves on Service Water Supply to Diesel Generators TEST REQUIREMENT:
CV BASIS FOR RELIEF:. Valves cannot be exercised during power operation since this would require isolating all cooling water to the Diesel Generators. Valve opening is demonstrated by adequate cooling to the Diesel Generators during system surveillance.
ALTERNATE TESTING: Per LER 89-017 commitments,-both check valves will be verified to c. lose via_ disassembly and inspection during the 1990 refueling outage. Valve closure will then'be verified
-by positive means on an' alternating basis during each sub-sequent refueling outage.
Inspection on a staggered sampling basis provides reasonable assurance of the ability of these valves to perform their safety related function. Each valve is of the same design (manufacturer, size, model number and materials of construc-tion) and have the same service conditions'.
Therefore, the condition and performance of both valves should be similar.
If it is.found that the inspected valve's operability is in question, both valves will be disassembled and inspected during the same refueling outage.
Rev. 10 V-34' i
h p
RELIEF REQUEST BASIS NUMBER:
V3 h
f_
' SYSTEM:
VALVE:
SE-70-4A,B,C,D c
CATEGORY:
B
-CLASS:
3
- FUNCTION:
.RHR SW Pump Motor Cooling Outlet TEST REQUIREMENT: MT BASIS FOR RELIEF:
Valves cannot be independent 1y' stroke timed as no manual switch exists'for such operation.
(
' ALTERNATE TESTING: SE-70-4A,B,C,D will be exercised during pump. surveillance
. tests and will be considered to be operating satisfactorily upon demonstration of proper RHR SW pump operation and ade-quate motor cooling water flow.
Rev. 10 V-35
O RELIEF' REQUEST BASIS-p.
NUMBER:
-V4 1
SYSTEM:
Recirculation pump' VALVE:
2-2-7A/B, 2-2-8A/B
-CATEGORY:
C
' CLASS:
2 FUNCTION:
Excess flow check' valves for instrument isolation g_
TEST. REQUIREMENT: CV BASIS FOR RELIEF: Valves can only be verified to shut by leak testing which is performed during the refueling. outage hydrostatic test.
This test cannot be repeated during each shutdown since-the reac-ter vessel is not at pressure during cold shutdown. Valves cannot be exercised shut during power operation since shutting these would isolate instrumentation required for power operation.
ALTERNATE TESTING: Valves will be functionally tested each refueling outage.
Rev. 10 V __
_____________________________j
y
~ -
1 m
2.'Fi 1,
y s
s RELIEF REQUESTmBASIS-A u
,q y
- NUMBER:
V5' 1
a
~ Service and Instrument Air, Diesel GeneratorfAir Startingi SYSTEM-s LSystem) c l VALVE:
.AS1'and AS2 on each Diesel Generator-CATEGORY:'-
B-
-$ CLASS:..
3.
l FUNCTION::
Emergency Diesel' Air Start Solenoid Valvesc 7 TEST REQUIREMENT:
Q~
BASIS FOR RELIEF:
- It.isLimpractical-tomeasure'the.limitingvalueoffull-stroketimeof[these, valves., These, valves do.'not.have remote position indication. Measuring the'
' stroke. time'of.these valves'by observing stem: travel'would require-
-disassembly of.the operator. -The. safety 1 function of these valves,:as a4 pair,:isLto,open to support the startup,ofotheir. respective diesel to' provide!
' rated: frequency and voltage;in,less than: thirteen seconds.afSuccessful;startup; of each emergency diesel. generator within the.above.specified conditions?
'is; dependent.upon..thefproper operation.and speed of these valves.1 7
Measuring startup time of each emergency. diesel generator-is an.cindirect method of verifying the operability of'these valves and meets ~the intent of Lthe Code.' ~Upon failure of the diesel generators.to start as. required,-
corrective action shall' be taken.to -assure proper diesel startup conditionsi.
ALTERNATE'. TESTING:
F
~These valves shall be' full-stroke tested on a quarterly basis using the.
l
. emergency diesel generator startup times as an indirect indication of valve-
operability.
o 1
l1 l
s 2Rev. 10
. V-37 l
c.
i.. >
RELIEF REQUEST BASIS l
, NUMBER:
V6 i
. SYSTEM:
Nuclear. Boiler VALVE:
V2-27A, 96A.
I
-CATEGORY:'
C CLASS:-
1,.
FUNCTION:
Feedwater Checks for HPCI/RCIC Operation 1
\\
~
S i' TEST. REQUIREMENT: CV l
BASIS FOR' RELIEF:
Valves are required to be open during both power operation and HPCI/RCIC operation..The valves are required to close for primary containment.. isolation. Closure:of-the valves-
.during power operation will result in loss of.feedwater to the vessel. Closure of the valves during' cold shutdown would require removing the only mechanism of vesselilevel control i
(via reactor water cleanup' system).
ALTERNATE TESTING.
I J
C Valves will be exercised to the fully open position by the' l
proper operation of>the feedwater system at startup. -The valves will be exercised to the fully closed position each j
refueling outage.during leak testing in'accordance with Relief Request Basis Number GV3.
i
-l I
l 1
i l
.I 4
l l
l l
s Rev. 10 V-38
__-_-____-_--_____:__-----__________--___--__-_-___-________-____.___--___-__-________-__-_--___--_-_-__-___i
-RELIEF REQUEST BASIS NUMBER:
V7 SYSTEH:
Nuclear Boiler VALVE:
V2-28A/B CATEGORY:
C CLASS:
1-FUNCTION:
Inboard Feedwater Check Valves TEST REQUIREMENT:
CV BASIS FOR RELIEF:
Valves are required to be open during both power operation and HPCI/RCIC operation. The valves are not required to i
close for primary containment isolation as they have been exempted from leak testing as described in the Vermont Yankee Primary Containment Leak Rate Testing Program. However, I
verification of closure upon cessation of flow will be per-formed as described below.
Closure of the valves during power operation will result in loss of feedwater to the vessel. Closure of the valves during cold shutdown would require removing.the only mecha-nism of vessel level control (via reactor water cleanup system).
ALTERNATE TESTING:
Valves will be exercised to the fully open position by the l
proper operation of the feedwater system at startup.
To verify proper closure upon cessation of flow, the valves will be partially disassembled and inspected to verify clo-l sure and that valve internals are structurally sound.
The
)
disassembly of each valve will be performed on a staggered j
sampling basis, one valve during each refueling outage.
j i
Inspection on a staggered sampling basis provides reasonable assurance of the ability of these valves to perform their safety related function.
Each valve is of the same design (manufacturer, size, model number and materials of construc-tion) and have the same service conditions.
Therefore, the condition and performance of both valves should be similar.
If it is found that the disassembled valve's operability is in question, the alternate valve will also be disassembled and inspected during the same refueling outage.
Rev. 10 V-39 I
1
,-- -- :w -- -
i RELIEF REQUEST BASIS' i.
p NUM8kR:
V8-g SYSTEM:
< Nuclear Boiler VALVE:
V2-28A/B l
CAIEGORY:
A CLASS:
1 l
FUNCTION:
Feedwater Checks for HPCI/RCIC Operation TEST' REQUIREMENT:
LT BASIS =FOR RELIEF:
The valves need not close to provide primary' containment iso-lation. This is based on the Appendix J testing of.the out-board feedwater check valves, the water seal on the inboard check valves, and the plant, capability to maintain a pressure greater than Pa on the Feedwater System. This basis was approved by the NRC inLthe SER transmitted by letter,
- 0. G. Eisenhut, NRC, to J. B. Sinclair, VYNPC, dated
' August 19, 1983.
ALTERNATE' TESTING: None j
l Rev. 10 V-40
_._p p
RELIEF REQUEST BASIS' l
l.!:
l NUMBER:
V9 SYSTEM:
Nuclear Boiler
-VALVE:
V2-37A - D
-CATEGORY:
C CLASS:
2 FUNCTION:
MSRV Air Supply Accumulator Check Valves TEST REQUIREMENT: CV BASIS FOR RELIEF: Valves'are normally closed and open only upon exercising of the Main Steam Relief Valves, RV2-71A-D. Valves can not be exercised seperately from the MSRV's as this would require isolating the control air of the MSRV's.
ALTERNATE TESTING: Valves will be verified to close'during leak testing as
-described in Relief Request Basis Number V10.- Valves will be l.
verified to open during exercising of the MSRV's as described
.I in Relief Request Basis Number V11..
Rev. 10 V-41
.~.
V' RELIEF REQUEST BASIS e
NUMBER:
VIO g
SYSTEM:
Nuclear Boiler r
b
' VALVE:
-V2-37A-D.
CATEGORY:
AC CLASS:
2 FUNCTION:
MSRV Air. Supply Accumulator Check Valves TEST REQUIREMENT:
LT (IWV-3426)
BASIS FOR RELIEF:
F
References:
1)
Letter, USNRC to VYNPC,. dated January 11, 1980, "IE Bulletin 80-01, Operability of ADS Pneumatic Supply".
L 2)
Letter, VYNPC to USNRC, dated January 18, 1980,~" Response to IE Bulletin 80-01".
3)
Letter, VYNPC to USNRC, dated January 25, 1980, " Supplementary Information in Response to IE Bulletin 80-01".
- 4) Letter, USNRC to All Licensees of Operating Plants, dated-October 31, 1980, NUREG-0737.
5)
Letter, VYNPC to USNRC, dated May 15, 1981, "NUREG-0737, Item II.K.3.28
" Verify Qualification of Accumulators on Automatic Depressurization System Valves".
6)
Letter, USNCR to VYNPC, dated May 11, 1983, " Request for Additional Information - NUREG-0737, Item II.K.3.28,
' Qualification of ADS Accumulators".
- 7) Letter, VYNPC to USNRC, dated December 5, 1983, "NUREG-0737, Item II.K.3.28".
- 8) Letter, USNRC to VYNPC, dated July 16, 1984, " Request for Additional Information - MPA F-55 (TMI II.K.3.28)
" Qualification of ADS Accumulators per 10 CFR 50.54 (f)".
- 9) Letter, VYNPC to USNRC, dated September 7, 1984, "NUREG-0737, Item II.K.3.28, Request for Additional Information on the Qualification of ADS Accumulators per 10 CFR 50.54()".
- 10) Letter, VYNPC to USNRC, dated January 24, 1985, "NUREG-0737, Item II.K.3.28, Request for Additional Information on the Qualification of ADS Accumulators".
11)
Letter, USNRC to VYNPC, dated March 4, 1985, " Verify Qualification of Accumulators on ADS Valves (II.K.3.28, MPA F-55)".
Rev. 10 V-42
=
i BASIS FOR RELIEF (Cont.)
The safety; function of valves V2-37A-D is to assure that the Main Steam Relief Valve (MSRV) accumulators remain at pressure in the event of a loss of header pressure. This is equal to the nominal system pressure.
The time period required for the MSRV to be operable is assumed to be 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
This is based on the standard practice cooldown rate of 100*F/hr.
From a saturation temperature of 544.6*F at 1000 psig to 327.8'F at 100 psig yields a drop of 216.8'F, or 2.17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> to shutdown. Assuming 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for operator action prior to depressurization, the time required for MSRV. operability is set at 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. This. time period also bounds all accident scenerios pre-sented in the Vermont Yankee FSAR.
Therefore, 100 psia - 64 osia 12 psig/hr.
=
3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> This methodology was approved by the NRC in the SER contained in Reference 11.
ALTERNATE TESTING:
Perform leak testing, analysis and corrective action in accordance with IWV-3420 with the exception that the maximum acceptable leakage rate shall be equal to 12 psig/hr with a initial test pressure of 100 psig.
Rev. 10 V-43
RELIEF, REQUEST BASIS T
NUMBER:
V11 SYSTEM:
Nuclear Boiler.
VALVE:
RV2-71A-D, SV2-70A/B CATEGORY:
'C CLASS:
1-FUNCTION:
Automatic Depressurization/ Overpressure Protection TEST REQUIREMENT: SRV (IWV-3512, IWV-3513)
BASIS FOR RELIEF:
- The present program for testing Main Steam Relief and Safety
. Valves as described in the Vermont Yankee Inservice. Testing.
Program is more conservative than the test frequency
. described in IWV-3511. Per the IST Program, all Main Steam Relief and Safety Valves are' tested every two refuel outages.
The' valves that are removed each refuel oucage for testing are either tested and returned to service or replaced with a-previously tested spare valve.
In the case where the valves are both tested and returned to service during a single refuel outage, additional testing.in full compliance with IWV-3513 will be performed should any valve fail to function properly during testing.
In the case where the valves are replaced with a previously tested spare, full compliance with IWV-3513 is not practical.
Should one valve fail to function properly'during testing, compliance with the increase in.the testing population (NF12) is performed since 50% of the valves are presently tested each refuel outage. However, should, additional valves fail l
to function properly, testing of all valves is not practical L
since the removed valves are not tested for as-found con-ditions until a convenient time after the refuel outage.
Therefore, the plant could be operating before it could be L
determined whether or not the removed valve fails to function l'
within Technical Specifications and Code Requirements.
ALTERNATE TESTING:
l-The Main Steam Relief and Safety Valves will be tested in i
accordance with the frequency stated in the IST Program. The H
analysis and reporting of failures shall be in accordance with the Licensee Event Report System, 10 CFR 50.73.
L Rev. 10 V-44 L
t RELIEF REQUEST BASIS NUMBER.:
.V12 L
SYSTEM:
Nuclear Boiler I
L VALVE:
RV2-71A-D, SIA-D l
CATEGORY:
B
- CLASS:
1 FUNCTION:
Automatic Depressurization I
TEST REQUIREMENT: Q BASIS FOR RELIEF: Valves cannot be exercised during power operation since failure in the open position would require tripping the reac-tor. Also, live steam would be discharged to the suppression pool which would heat the water and pressurize the contain-ment. Valves cannot be exercised during cold shutdowns since steam is required to stroke the main piston in the valve.
Based on the following references, the testing of each relief valve at a frequency of once per operating cycle is assessed to be adequate by Vermont Yankee and the industry.
In a letter from Brian K. Grimes of the NRC to All Boiling Water.
Reactor Licensees dated July 16, 1979 regarding relief and safety-relief valves, it states that "we have concluded that implementation of a requirement for increased surveillance testing would not be the most effective way of assuring safety-relief valve reliability." Also referenced is a letter from Darrel G. Eisenhut of the NRC to All Operating Reactor Licensees dated May 7, 1980 regarding the Five Addi-tional TMI-2 Related Requirements to Operating Reactors.
Item II.K.3.16 entitled Reduction of Challenoes and Failures of Relief Valves - Feasibility Study and System Modification states that, "Those changes which are shown to-reduce relief valve challenges without compromising the performance of the relief valves or other systems should be' implemented."- Ver-mont Yankee's response to an NRC suggested Tech. Spec. change dated February 2, 1978 states that "Both General Electric Company and Target Rock strongly recommend that these valves be manually operated only when absolutely necessary. The only time we consider to be absolutely necessary, other than if plant conditions warrant, is once a cycle."
ALTERNATE TESTING: During power accension after a refueling outage, each relief valve will be manually opened to full stroke with the reactor at low pressure until the thermocouple downsteam of the valve indicates fluid is flowing from the valve.
(Note:
Proper
)
operation of RV2-71A-D verifies operability cf S1A-D).
Rev. 10 V-45
a-RELIEF REQUEST-BASIS NUMBER '
V13 SYSTEM:
Nuclear Boiler ~
VALVE:
V2-278,-V2-968 CATEGORY:
C CLASS:
2 FUNCTION:
.Feedwater Checks for HPCI/RCIC Operation TEST REQUIREMENT:
CV BASIS FOR RELIEF: Valves are required to be open during power operation. The valves are required to close for HPCI/RCIC operttion and pri-mary containment isolation. Shutting these valves will cause
.a loss of feedwater to the vessel. Testing via the HPCI/RCIC systems would cause thermal shocking of the feedwater nozzles and could result in damage to reactor internals. Testing the valves during cold shutdown would require removing the only mechanism of vessel level control (via reactor cleanup system).
ALTERNATE TESTING: Valves will.be exercised to the fully open position by the proper operation of the Feedwater System at startup. 'The valves will be exercised to the fully closed position each refueling outage during leak testing in accordance with Relief Request Basis Number GV3.
l l'
1 Rev. 10 V-46
_r" I'
2
. RELIEF REQUEST BASIS
' NUMBER:
'Vid
' SYSTEM:
Nuclear Boiler-VALVE:
2-62-A-D, 2-64-A-D, 2-73-A-H, 2-305'A/B
' CATEGORY:
C CLASS:
2 FUNCTION:
Excess Flow Check Valves for Instrument Isolation TEST REQUIREMENT:
CV BASIS FOR RELIEF: Valves can only be verified to shut by leak testing which is performed during the refueling outage hydrostatic test.
This test cannot be repeated during each shutdown since the reac-tor vessel is not at pressure during cold shutdown. Valves-cannot be exercised shut during power operation since shutting these would isolate instrumentation required forL power operatio:.
ALTERNATE TESTING: Valves will be functionally tested each refueling outage.
i 1
i Rev. 10 V-47
RELIEF REQUEST BASIS-NUMBER:
V15'
' SYSTEM:
l Core Spray VALVE:
V14-12A/B, V14-13A/B CATEGORY:
'A-CLASS:
2, FUNCTION:
Pressure Boundary Isolation TEST REQUIREMENT:
LT
REFERENCES:
1.
Generic NRC letter, D. G. Eisenhut, NRC, to D. E. Vandenburgh, VYNPC, dated February 23, 1980.
2..
Letter,'O. E. Vandenburgh, VYNPC, to D. G. Eisenhut, NRC, " LWR Primary Coolant System Isolation Valves", WVY 80-41, dated March 14, 1980.
3.
Letter, T. P. Ippolito, NRC, to R. L. Smith, VYNPC, dated August 8, 1980.
Includes " Technical Evaluation Report (TER), Primary Coolant System Pressure Isolation Valves", dated July 21, 1980.
4.
Generic NRC letter 87-06, H. R. Denton, NRC, to All Holders of Operating Licenses, dated March 13, 1987.
5.
Letter, W. P. Murphy, VYNPC, to T. E. Murley, NRC,
" Response to Generic Letter 87-06, Periodic Verification of Leak-Tight Integrity of Pressure Isolation Valves",
FVY 87-64, dated June 11, 1987.
BASIS FOR RELIEF:
Pressure isolation valves (PIVs) are defined for each inter-face as any two valves in series within the reactor coolant pressure boundary which separate the high pressure reactor coolant system (RCS) from the attached low pressure system.
Leakage of such PIVs could result in overpressurization of the low pressure system with possible resultant rupture and loss of reactor coolant outside of containment.
In response to References (3) and (4), Reference (5) provided a listing of PIVs at Vermont Yankee. The NRC, via Reference L
(1), stated that the integrity of such valves is adequately i
assured either by continuous or periodic monitoring of downstream pressure or by the performance of leak testing.
Rev. 10 V-48 I
l
y..
s,.
3 w
s >
j.3.g-u,
3 -
e ja s
i
.fg -] ;
e l ^~ z l;
~ BASIS FOR RELIEF (Cont.)-
a g--
d' l R b
b
'For Ehese valves,' continuous' monitoring of the downstreamL
- pressure at.this interface _is provided by'PS-88-47A/8,.
. >.q r,':
located downstream of V14-12A/B.
?
y l ALTERNATE'TESTINGi None.
1 5
. +.
(
i 4
l' N
?
g
~
i i
t Rev. 10 V-49 t:
n_--.
t RELIEF REQUEST BASIS-1 NUMBER:
V16 SYSTEM:
- Core Spray VALVE:
V14-31A/B-
. CATEGORY:
C CLASS:
2 FUNCTION:
Excess flow check valves for instrument' isolation TEST REQUIREMENT:
CV.
BASIS FOR RELIEF: Valves can only be verified to shut by leak testing which is performed during the refueling outage hydrostatic test. This
' test cannot be. repeated during each shutdown since the reac-tor vessel is not at pressure during cold shutdown. Valves cannot be exercised shut during power operation since shutting these would isolate instrumentation required for power operation.
ALTERNATE TESTING: Valves will be functionally tested each refueling outage.
li-Rev. 10 V-50
f 3
RELIEF REQUEST BASIS
. NUMBER:
V17:
j, ;
SYSTEM:
Core Spray VALVE :
V14-33A/8 CATEGORY:
C-n CLASS:
2 FUNCTION:
Core _ Spray Pressurizing Line Check Valve TEST REQUIREMENT: ' CV L
BASIS FOR RELIEF:
- There is no test. loop available to. regularly exercise these valves. _Their proper operation is assured through continuous Core Spray discharge header pressure monitoring.and by veri-fication of' acceptable Core Spray parameters during system surveillance,.
ALTERNATE TESTING:
Proper closure of V14-33A/B is verified during surveillance runs of the Core Spray pumps. This meets the intent of
- IWV-3522.
Rev. 10-V-51
RELIEF REQUEST. BASIS NUMBER:
V18
' SYSTEM:
High Pressure Coolant Injection
. VALVE:
SL23-37A-D
- CATEGORY:
.C
.. CLASS:
2 FUNCTION:
Excess flow check valves for instrument isolation
' TEST REQUIREMENT: CV BASIS FOR RELIEF: Valves can only be verified to shut by leak testing which.is performed during the refueling outage hydrostatic test. This
' test'cannot be repeated during each shutdown since the reac-tor vessel is not at pressure during cold shutdown.- Valves-cannot be exercised shut during power operation since shutting these would isolate instrumentation required for power operation.
ALTERNATE TESTING: Valves will be functionally tested each refueling outage.
1 1
Rev. 10 V-52
- RELIEF REQUEST BASIS a
NUMBER:
V19
- SYSTEM
High Pressure Coolant Injection VALVE:
V23-50A CATEGORY:
B CLASSi 2-FUNCTION:
Inlet Valve for HPCI Equipment' Cooling Flow-TEST REQUIREMENT:- MT-BASIS FOR RELIEF: Valve cannot be independently stroke timed as no manual switch exists for such' operation.
ALTERNATE TESTING: V23-50A will txe exercised during pump surveillance tests and will be considered to be operating satisfactorily upon demonstration of proper HPCI pump operation and adequate flow-to the Lube Oil Cooler and Gland Seal Condenser.. In addi-tion, valve exercising will be observed via remote indication.
Rev. 10 V-53
RELIEF REQUEST BASIS.
l H
' NUMBER:
V20 SYSTEM '
' Control Rod Drive Hydraulic VALVE:"
'V3-13-114, V3-13-115, V3-13-126, V3-13-127' CATEGORY:
B or C CLASS:
2'
- FUNCTION:
Control rod drive scram
' TEST REQUIREMENT: Q or.CV BASIS FOR RELIEF:
Exercising these valves during power operation would require-scramming the plant or an undesirable. reactor transient.
ALTERNATE TESTING: Since scram insertion times are representative of valve operability and stroke times, alternate testing will be per-formed in accordance with Tech. Spec. Section 4.3.C.1 and 2.
This section requires that all control. rods be subjected to scram-time measurements on a refueling outage basis. Also, this section requires that 50% of the control rods be measured for scram times every 16 to 32 weeks. An evaluation is required that provides reasonable assurance that proper control rod drive performance is being maintained. These.
tests adequately verify valve operability and stroke times.
Rev. 10 V-54 l
I t
RELIEF REQUEST BASIG-l' 2
l0l NUMBER:
V211 1;
' SYSTEM:
Control Rod Drive Hydraulic-VALVE:
- V3-13-115 LCATEGORY:
.C' CLASS:-
2
. FUNCTION:
Control Rod Drive Scram TEST. REQUIREMENT:
CV-BASIS FOR RELIEF:.C1hsure verification of these valves requires'that the control. rod drive pumps.be stopped to depressurize the charging water header...This test cannot.be performed during power! operation because stopping the pumps results in a loss of cooling water to all control rod drive mechanisms and' seal
~
damage could result. Additionally, this test cannot be per-formed during each cold shutdown because the control rod drive pumps supply seal water.to'the reactor recirculation
. pumps.
ALTERNATE TESTING: Vermont Yankee performed the above described pressure decay leak. test during the 1989 refueling outage. This was the-first test of this kind performed since original plant start-up in.1972. Results of the 1989 test were.very similar to-the 1972 test.
(Note: Valve leakage is determined by depressurizing the charging' water header and observing accu-mulator. pressure decay corresponding to'each 115 check valve.
During'the 1972 startup test, accumulators maintained
~
pressure for at:1 east 16 minutes.
1989 test results showed the worst case accumulator pressure decay to be a decrease to 920 psig after 18 minutes which is still well above'the.
acceptance criteria pressure of 800 psig. Therefore,-the exceptional leak tight integrity of these valves was recon '
firmed after 17 years of operation.)
Based on the above, valve closure will be verified on an alternating refueling outage basis by stopping the control-rod drive pumps and observing control rod drive accumulator pressures. Proper valve closure will be demonstrated by-accumulators maintaining adequate charging pressure for.5 minutes after the pumps are stopped.
Rev. 10 V-55 i
i j.:
RELIEF REQUEST BASIS
' NUMBER:
V22 iif SYSTEM:'
Control Rod Drive Hydraulic
- //
. VALVE:
V13-162A/B.
' CATEGORY:
.C CLASS ~
3 FUNCTION:
Scram Discharge Volume Vent Check Valves:
>TE'T REQUIREMENT: CV S
BASIS FOR RELIEF: Valves cannot be exercised during power operation since this would require taking"the CRD. system out of service.
Operability of these valves is demonstrated by' decreasing scram discharge volume water level upon reset from SCRAM.
ALTERNATE TESTING:~None Rev. 10 V-56
.K RELIEF REQUEST BASIS
(
'.c NUMBER:
V23
' SYSTEM:
-VALVE:
V11-16, V11-17 CATEGORY:
C' CLASS:
1
. FUNCTION:
SLC Injection into Reactor TEST REQUIREMENT: CV BASIS FOR RELIEF:
Exercising these valves during power operation would require injecting borated water into the reactor coolant system.
This would create a reactivity excursion and potential for reactor trip.
Injection of demineralized water would require removing the system from service to clean the borated solu-tion from the piping and replacing the explosive actuated valves. This system is required for power operation.
ALTERNATE TESTING: Valve opening will be demonstrated each refuel outage by the system flow test directly into the reactor vessel.
Valve closure was verified during the 1989 refueling outage via leak-testing in accordance with IWV-3420. This was the first leak test of record ever performed on these valves and occurred after 17 years of service. Valve V11-16 exhibited no leakage and valve V11-17 exhibited very. limited leakage that was well below IWV-3420 limits..(Note: Observed leakage of V11-17 was 0.428 ml/ min versus an acceptance cri-teria of not greater than 550 ml/ min.) Based on.the above test results, the fact that these valves are rarely cycled, and that the internals are in a clean demineralized water environment, valve closure will be demonstrated on an alter-nating refueling cycle basis. This demonstration will con-
~
tinue to consist of leak testing in accordance with IWV-3420 i
limits.
-Rev. 10 V-57
-__________---__-__-__-_A
by I
' RELIEF! REQUEST BASIS e
HUMBER:
V24' SYSTEM:
' Standby Liquid Control VAiVE:
SR-39A/B CATEGORY:
C CLASS:
2 FUNCTION:
SLC System Overpressure Protection
' TEST REQUIREMENT: SRV (IWV-3511)
BASIS FOR RELIEF: The present program for testing the SLC relief valves as des-cribed in the Vermont Yankee Inservice Testing Program is more conservative than the tee,t frequency described in IWV-3511.
Per the IST Program, both valves are tested each refuel outage.
ALTERNATE TESTING: Continue to test the SLC relief valves per the requirements of the Inservice Testing Program.-
Rev. 10 V-58
RELIEF REQUEST BASISf
- NUMBER:
V25
- SYSTEM:
Residual Heat Removal' VALVE:
V10-17, V10-27A/8, V10-46A/B CATEGORY:
A CLASS:,
1 FUNCTION:.
. Pressure Boundary Isolation
' TEST REQUIREMENT: LT
REFERENCES:
1.
Generic NRC letter, D. G. Eisenhut, NRC, to D. E.'Vandenburgh, VYNPC, dated February 23, 1980.
- 2.. Letter, D. E. Vandenburgh, VYNPC, to D. G. Eisenhut, NRC,
" LWR Primary Coolant System Pressure Isolation Valves",
WVY B0-41, dated March 14, 1980.
3.
Letter, T. P. Ippolito, NRC, to R. L. Smith, VYNPC, dated August 8, 1980.
Includes " Technical Evaluation Report' (TER), Primary Coolant System Pressure Isolation Valves",
dated July 21, 1980.
4.
Generic NRC letter 87-06, H. R. Denton, NRC, to All Holders of Operating Licenses, dated March'13, 1987.
- 5. ~ Letter, W. P.. Murphy, VYNPC, to T. E.'Murley, NRC,
" Response to Generic Letter 87-06, Periodic. Verification of Leak-Tight Integrity of Pressure Isolation Valves",
FVY 87-64,. dated June 11,.1987.
BASIS FOR RELIEF:
Pressure isolation valves (PIVs) are defined for each inter-face as any two valves in series within the reactor coolant pressure boundary which separate the high pressure reactor coolant system (RCS) from the attached low pressure. system.
Leakage of such PIVs could result in overpressurization of the low pressure system with possible resultant rupture and loss of reactor coolant outside of containment.
i In response to References (3) and (4), Reference (5) provided a listing of PIVs at Vermont Yankee.
The NRC, via Reference I
(1), stated that the integrity of such valves is adequately assured either by continuous or periodic monitoring of downstream pressure or by the performance of leak testing.
l Rev. 10 V-59 l
y-BASIS FOR RELIEFi-(Cont.)'
For valve V10-17,.. continuous monitoring of the downstream pressure:is provided by PS-10-118.
For valves-V10-27A/B and' V10-46A/B, continuous. monitoring of the downstream pressure-at this' interface is provided by PS-10-122A/B, located downstream of:V10-27A/B. -In addition, monitoring of'the pressure downstream of valves V10-46A/B is performed daily by reading PI-10-100A/B.
ALTERNATE TESTING: None.
Rev. 10 V-60'
+
JO RELIEF REQUEST BASIS:
1
. NUMBER:
V26
' SYSTEM:
Residual Heat Removal VALVE:.
V10-89A/B CATEGORY:
B CLASS':
3 FUNCTION:
Flow Control TEST REQUIREMENT: MT BASIS FOR RELIEF: Valve is a modulating type valve. Stroke time is not an l
appropriate reference' parameter.
j s
ALTERNATE. TESTING: Proper valve operation is verified through normal system operation during the pump tests.
~
l-l l
s.
1 Rev. 10 V-61 i
L o
RELIEF REQUEST BASIS
. NUMBER:
V27-SYSTEM:
Residual Heat Removal-VALVE:
V10-36A/B g,
CATEGORY:
C.
CLASS:.
2
- FUNCTION:
Residual Heat Removal Pressurizing Line Check Valve TEST REQUIREMENT: CV BASIS FOR RELIEF: There is no test loop.available'to regularly exercise these-valves. Their proper operation is assured through continuous Residual Heat Removal discharge header pressure monitoring-and by. verification of acceptable Residual Heat Removal para-
. meters during system surveillance.
ALTERNATE TESTING: Proper closure of V10-36A/B is verified during surveillance runs of the Residual Heat Removal pumps. This meets the
' intent of IWV-3522.
Rev. 10 V-62
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ - - - _ _ _ - _ ~
! f"k..
RELIEF REQUEST BASIS F
NUMBER:
V28-l,
. SYSTEM:
. Reactor Core. Isolation Cooling VALVE:
-J q
CATEGORY:
C 1
1 CLASS:
2 l
FUNCTION:
Excess flow check valves for instrument isolation
_ TEST REQUIREMENT: CV BASIS FOR RELIEF: Valves can only.be verified to shut by leak testing which is performed'during the refueling outage hydrostatic test. This test cannot be repeated during each shutdown since the reac-
' tor vessel is not at pressure during cold. shutdown. Valves q
cannot be exercised ~ shut during power operation since shutting these would isolate instrumentation required for
' power operation.
ALTERNATE TESTING: Valves will be functionally tested each refueling outage.
1 Rev. 10 V-63
r.
_t i1 c
RELIEF. REQUEST BASIS' Y
9 e.
' NUMBER:
V29 Vis' SYSTEM:
Reactor Core Isolation Cooling
-' VALVE :
Turb. Gov.-
CATEGOR'Y':
B:
. CLASS:
2' N
' FUNCTION:
Modulating Valve
[
. TEST. REQUIREMENT: MT
- BASIS FOR RELIEF: Valve is-a modulating type valve. ' Stroke time is not_an
' appropriate reference parameter.
ALTERNATE TESTING: Proper valve operation is. verified through normal system operation during the pump tests.
II
- Rev. 10 V - _ - _ _ _ _ _ _ - _ _ _ _ _ _ - _ - _ _ -. _ - - - - - _ _ _ _ _ _ _ _ _ _
L
- r s
k RELIEF REQUEST BASIS s
i i NUMBER:--
.V30.
1 LSYSTEM:
Reactor Core Isolation Cooling
.' VALVE :
V13-70, V13-133
'CATEGORYi C
LCLASS:
2 and 3 FUNCTION:
Gland Seal Condensate Pump Discharge Check Valves LTEST REQUIREMENT:
CV
. BASIS.FOR RELIEF: Proper operation of this pair of valves, which are. installed in series, cannot be individually verified in the closed direction due'to the piping arrangement.
- ALTERNATE TESTING:' Valves will be verified to open during normal. Reactor Core Isolation Cooling surveillance testing. Closure of,at least one valve in the pair is confirmed via continuous monitoring-of Gland' Seal Condenser level.
Since these valves cannot be isolated without affecting system operability and based on the above monitoring, verifi-cation that each valve functions'in the closed direction will be performed once each operating cycle via disassembly.
or other positive means.
Rev.'10 V-65
RELIEF REQUEST BdSIS
' NUMBER:
- V31-
~ SYSTEM:-
Primary Containment and Atmosphere Control VALVE:
V16-19a5 A to J CATEGORY:-
A-CLASS:
2 FUNCTION:
Torus-drywell Vacuum Breakers TEST REQUIREMENT: CV BASIS FOR RELIEF: Testing of valve opening force as required by IWV-3522(b) can not be performed during power operation since this testing would cause the loss of the differential pressure between the drywell and the suppression chamber. This DP is a required condition of plant operation.
ALTERNATE TESTING: Once'every 3 months and following any release of energy to the suppression chamber each suppression ' chamber-drywell vacuum-breaker shall be exercised. During each refueling outage all suppression chamber-drywell vacuum breakers shall be tested to determine that the applied force at all valve positions does not exceed that equivalent to 0.5 psi acting on the suppression chamber face of the valve disk.
During each refueling outage at least 2 of the 10 suppression chamber-drywell vacuum breakers shall be disassembled and inspected.
If deficiencies are found such that Tech. Spec.
Section 3.7.A.6 can not be met, all vacuum breakers shall be inspected and deficiencies corrected.
Rev. 10 V-66
If RELIEF REQUEST BASIS-i i.
V32 NUMBER:-
SYSTEM:
Primary Containment and Atmosphere Control:
y l VALVE:
V16-19-5 A to J CATEGORY:
A CL SS:
2 FUNCTION:
Torus-drywell vacuum breakers l
TEST REQUIREMENT:
LT
' BASIS FOR-RELIEF: Valves cannot be leak tested individually ALTERNATE TESTING': Leak test will be done which will demonstrate that with an initial differential pressure of not less than 1.0 psi, the differential pressure decay. rate shall not exceed the equiva-lent of the leakage rate through a 1-inch orifice.
l f.
r
'Rev. 10 V !
RELIEF' REQUEST BASIS-e
. NUMBER:
'V33 SYSTEM:
Reactor. Water. Cleanup VILVE:
V12-28A/B CATEGORY:
C
' CLASS:
3 FUNCTION:
React'or Water Cleanup Pump Discharge Check Valves TEST REQUIREMENT:.CV BASIS FOR RELIEF: Due to the operating characteristics of the Reactor Water Cleanup system, the two subject valves cannot each be verified to close on a quarterly basis.
ALTERNATE TESTING:~Both valves were disassembled and refurbished during the 1989 refueling outage. During each subsequent refueling outage, both valves will be verified to close via observation of-
' appropriate system indication or by other positive means.
Rev. 10 V-68
gr a
~-
F-h
>~
RELIEF REQUEST BASIS L
NUMBER:
- V34' SYSTEM:
Control Room Ventilation Cooling VALVE:
SCW-8A CATEGORY:<
C.
~ CLASS 2.
3'
' FUNCTION:
Chilled Wat'er-Pump Discharge Check Valve
- TEST REQUIREMENT: CV BASIS FOR RELIEF: Valvecannotbe.exercisedclosed[duringsystemoperation since this'would require isolation of the Control Room
. Chilled Water system and related ventilation equipment.
ALTERNATE TESTING: Valve opening is demonstrated by normal system operation and pump surveillance testing. Closure will be verified annually:
as climatic conditions permit via valve disassembly or by placing the system-in an alternate configuration and observing appropriate system pressure indication.
Rev. 10 V-69
____._a___.m
_.m___.__..--___-____-._____
RELIEF REQUEST-BASIS; f
L NUMBER:
V35 h'
' SYSTEM:
Nuclear Boiler Vessel Instrumentation
[
' VALVE:
2-3-11,~2-3-13A/S, 2-3-15A/B, 2-3-17A/B, 2-3-19A/B, 2-3-21A-D, 2-3-23A-D, 2-3-25, 2-3-27, 2-3-29A/B, 2-3-31A-H, 2-3-311-Q, 2-3-33, 2-3-35.
CATEGORY:
C
!=
CLASS:
2
' FUNCTION:
Excess, flow check valves for instrument isolation TEST REQUIREMENT:
CV-BASIS FOR RELIEF:. Valves can only be verified to shut by leak testing which is performed during the refueling outage hydrostatic test.
This test cannot be repeated during each cold shutdown since the reactor vessel is not at pressure during cold shutdown.
Valves cannot be exercised shut during power operation since shutting these would isolate instrumentation required for power operation.
~ ALTERNATE TESTING: Valves will be functionally tested each refueling outage.
Rev. 10 V-70
D",.-g
- RELIEF REQUEST BASIS:
NUMBER:
V36 SYSTEM:
-TIP VALVE:
Ball A-C CATEGORY:
A CLASS:
2 FUNCTION:
Primary Containment' Isolation TEST REQUIREMENT:- Remote' Position Indicator Verification (IWV-3300)
BASIS FOR RELIEF:
Direct visua1' verification of position would require-
. disassembly of the valve enclosures as the limit switches are contained within the enclosures.
ALTERNATE TESTING:
Positive verification of full opening of the. valves is shown by successful insertion of the Transversing In-Core Probe through the valve. This is performed on a minimum frequency of once per month during operation.: Positive verification of.
full closing of the valve is shown during each refueling outage by successful leak testing in accordance with Relief Request Basis Number GV-3.
L l
Rev. 10 V-71 L__
RELIEF REQUEST BASfS NUMBER:
GV-1 CODE PARAGRAPHS:
IWV-3417(b) and IWV-3523 concerning corrective action prior I
to startup.
BASIS FOR RELIEF:
The Vermont Yankee Technical Specifications and j
Administrative Procedures describe various limiting con-ditions for operation and startup prerequisites including verification that all cold shutdown surveillance procedures are complete and acceptable. These controls comply with the above referenced requirements and are more appropriately used as a basis for plant startup.
ALTERNATIVE:
The Technical Specifications and Administrative Procedures will be used as the basis for determining plant startup readiness.
Rev. 10 V-72
RELIEF REQUEST BASIS i
NUMBER:
GV-2 CODE PARAGRAPHS:
IWV-3417
. BASIS FOR RELIEF:-
Recent analysis done by the ASME in developing ANSI /ASME Standard OM-10, " Inservice Testing of Valves", Draft 11, has resulted in revisions to the acceptance criteria and correc-tive actions for valve exercise testing.
Paragraph IWV-3417(a) states the following:
"If, for power operated valves, an increase in stroke time of 25% or more from the previous test for valves with full-stroke times greater than 10 seconds or 50% or more for valves with full-stroke times less than or equal to 10 seconds is observed, test frequency shall be increased to once each month until corrective action is taken,...."
These requirements do not consider the following points:
- 1) By comparing stroke times to the previous test, rather than a fixed reference value, long-term, slow degradation may go undetected until the maximum limiting value for the full-stroke time is reached.
- 2) By considering only increases in stroke times, valve problems which result in decreases in stroke times (i.e.,
detached disk) may go undetected.
- 3) Certain power operated valves have very short stroke times. The ability to accurately.neasure these short stroke times with a hand-held stopwatch is difficult and not repeatable.
- 4) Based on data collected from several PWRs and BWRs, the operating characteristics of electric motor actuated valves are more consistent than those of pneumatic or hydraulically operated valves. Therefore, degradation of electric motor actuated valves can be more accurately determined.
- 5) As defined in the Inservice Testing Program, there is sufficient justification to test certain valves on either a cold shutdown or a refueling outage basis. The test frequency of these valves cannot be increased without jeopardizing plant operations.
Rev. 10 V-73
a
-RRB-GV-2l(Continued)
ALTERNATIVE TESTING:
Valve exercise testing will be performed under the following guidelines:
- 1) STROKE TIME ACCEPTANCE CRITERIA Test results shall be compared to the initial
. reference values or reference values established in.
accordance with 4 and 5 below.
a.
Electric motor operated valves with reference stroke times greater than'10 seconds shall exhi-bit no more than.115% change in stroke time when compared to the reference value, b.
Other power operated valves with reference stroke
' times greater. than 10. seconds shall exhibit rx) y more'than 125% change in stroke time when com-pared to the reference.value, c.
Electric motor operated valves with reference.
stroke times less than or equal to 10 seconds' sha11' exhibit no more than a 125% or il second change in stroke ~ time, whichever is greater, when l
compared to the reference value.
d.
Other power operated valves with reference stroke times less than or equal to 10 seconds shall l
i exhibit no more than 150% or il second change in stroke time, whichever is greater, when compared to the reference value.
i e.
Valves that stroke in less than two seconds may be exempted from Ic and-1d above.
In such cases the maximum limiting stroke time shall be two seconds.
- 2) CORRECTIVE ACTION a.
If a valve fails to exhibit the required change of position or exceeds the limiting values of full stroke time given in Table 1, the valve shall be immediately declared inoperable, b.
If a valve stroke time does not meet the accep-tance criteria of la through Id above, the test frequency shall be increased as follows:
- 1) For valves normally tested quarterly, the test frequency shall be increased to once each month.
1-L Rev. 10 V-74 I
i L
L RRB-GV-2 (Continued)
- 2) For valves normally tested during cold shut-down, the test frequency shall be increased to each cold shutdown, but not to exceed once per month.
- 3) For valves normally tested during refueling outages only, the test frequency shall remain at each refueling outaga.
c.
Valves declared inoperable may be repaired, replaced, or the data may be analyzed to deter-mine the cause of the deviation and the valve shown to be operating acceptsbly.
3.
REFERENCE VALUES Reference values shall be determined from the results of pre-service testing or from the results of in-service testing. These tests shall be performed under conditions as near as practicable to those expected during subsequent in-service testing.
Reference values shall only be established when the valve is known to be operating acceptably.
If the particular parameter being measured can be signifi-cantly influenced by other related conditions, then these conditions shall be analyzed.
4.
EFFECTS OF VALVE OR ACTUATOR REPLACEMENT, REPAIR, AND MAINTENANCE ON REFERENCE VALUES When a valve has been replaced, repaired or has undergone maintenance ' that could affect the valve's performance, a new reference value shall be deter-mined or the previous value reconfirmed by an in-service test run prior to the time.it is returned to service or immediately if'not removed from service, to demonstrate that performance parameters which could be affected by the replacement, repair or maintenance are within acceptable limits. Deviations between the previous and new reference value shall be identified and analyzed. Verification that the new value repre-sents acceptable operation shall be documented in the record of tests (IWV-6000).
' Adjustment of stem packing, limit switebrs, or control system valves, and removal of the bonnet, stem assembly, actuator, internals, or control system components are examples of maintenance that could affect valve performance parameters.
Rev. 10 V-75
- y, t
o 7-
<;p y
'I
. p:
/RRB-GV-2'(Continued)~
- 5. 'TO ESTABLISH AN ADDITIONAL SET OF REFERENCE VALUES-o If it'is'necessary.or desirable:for.some' reason,
'other<than stated in 4 above,'to-establish additionali q
reference values, an in-service test shall first be-l run at the conditions of..an existing set of reference;
-values and the results analyzed. lIf operation is; acceptable, a second test shall be performed.under.
I, the new conditions as soon as practical....The results of the second. test shall establish.the. additional" g
reference values. Whenever additional reference values'are established the. reasons'for.doing so shall be~ justified and documented'in the record of' tests.
(IWV-6000).
Rev. 10; V-76.
RELIEF REQUEST BASIS
. NUMBER:
GV-3 SYSTEM:
See attached listing VALVE:
See attached listing CATEGORY:
A or A-C CLASS:
1 or 2 FUNCTION:
Primary Containment Isolation
. TEST REQUIREMENT:
LT CODE PARAGRAPHS:
IWV-3421 through IWV-3427 BASIS FOR RELIEF:
IWV-3421 through IWV-3425:
The applicable leak test procedures and requirements for con '
tainment isolation valves are determined by 10 CFR 50, Appendix J.
Relief from Paragraphs IWV-3421.thorugh IWV-3425 is acceptable since the intent of these paragrapiis is met by the Appendix J requirements. This testing will continue'to give reasonable assurance that in the event of the postulated-
. loss-of-coolant accident, the total release of fission pro-ducts from the primary containment to the environs is limited such.that off-site doses would be well below the values specified in 10 CFR 100.
IWV-3426:
Paragraph IWV-3426 states that leakage rates may be specified by the Owner.
In this case, 10 CFR 50, Appendix J, Paragraph III.C.3 states that the combined leakage rate for all penetrations and valves subject to Type B and C tests shall be less than 0.60 La.
Additionally, Vermont Yankee Technical Specifications, Section 3.7.A.4, states that the leakage from any one isola-tion valve shall not exceed 0.05 La and the leakage from any one main steam line isolation valve shall not exceed 15.5 scf/hr at 44 psig (Pa).
IWV-3427(a):
Vermont Yankee Technical Specifications, Section 4.7.A.4 states that repair and retest shall be conducted to ensure compliance. Therefore, the intent of IWV-3427(a) is met.
Rev. 10 V-77 l
- __-_ _ _-_______ - -_--_ - - ____-__-__ _ a
x RRB-GV-3 (Csntinued)
IWV-3427(b):
Paragraph IWV-3427(b) requires:
1)' A doubling of the test frequency upon a reduction of the margin between the measured leakage rate and the maximum permissible rate by 50%, and 2)
Repair or replacement should a projection based on.
three or more tests indicate that the-leakage rate of.
the next scheduled test will exceed the maximum per-missible leakage rate by greater than 10%.
The above limits have been compared'to previous Appendix J 1eakage rate test data taken since 1976. This-comparison-suggests that the requirements of IWV-3427(b) do not' provide accurate predictions of future valve leakage in all cases since' increased valve leakage may not be a result of degradation.
When performing periodic Appendix J 1eak testing, factors other than degradation attribute to the final results. These factors may cause either an increase or decrease in the leakage rate, thereby making a determination of~the valve condition based solely on trending difficult. These factors are summarized as follows:
- 1) Boundary valves which define the test envelope have individual leakage characteristics which can change from use, packing age, and closure force. Since these factors can affect each boundary valve and all resulting.
leakage is assigned to the tested valve, a repeatable periodic leakage characteristic for the tested valve is difficult to determine. Field test data supports this fact as summarized below.
- 2) Due to operational requirements, boundary configuration changes may be necessary. This can affect leakage and indicate degradation of the tested valve that does not exist.
- 3) Due to operational requirements, testing may be per-formed by different methods. Test method and boundary changes make a repeatable periodic leakage charac-teristic for the tested valve difficult to determine.
The variance of the leakage rate test data and the difficulty in trending such data is shown by a study of the Appendix J 1eakage rate test data for valves 6" nominal pipe size and larger. Data from 1976 to the present was input into a computer program which performed least squares curve fits on the data.
Curves for 25 equations were fitted to the data for each valve. Equation coefficients, correlation coefficients, and the best fit curve was computed in each case.
In addition, 1
l Rev. 10 V-78
E
'RRB-GV-3 (Continu d).
. projections ~were made at' intermediate points.usingL the bestl
' fit curves. The average deviation'between the. projected and
~
actual test results was 145%.
In addition, the projections
+
F
.provided early indication of an actual failure only 20% of.
- the-time.
In summary, strict compliance with IWV-3427(b).may require an increase in valve testing, maintenance, and~ personnel radiation exposure without a compensating' increase in the level of' safety-since predicting future valve leakage is-statistically unreliable.:
b Relating to the' requirement of;IWV-3427(b) to conduct testing l
L duringl cold shutdowns, Relief. Request' Bases' contained within-the. Inservice Testing Program contain sufficient justifica.
O tion;to test certain valves only on a refueling, outage' basis.-
-The test frequency of these valves cannot be increased without'
. jeopardizing plant operations.
ALTERNATE TESTING:
Perform leak testing, analysis and' corrective actions.in accordance with the Vermont. Yankee Primary Containment Leak:
Rate Testing Program,-10 CFR 50, Appendix J.
In addition, all exemptions from testing _and testing methods. contained within the= Vermont Yankee Primary Containment Leak Rate Testing Program will be! equally applied to this Inservice Testing Program.
'Rev. 10 L
V-79
\\
L
.m m_m.__.-____________.
v f2 RELIEF REQUEST BASIS.GV-3 Listing of Systems and Valves
~ SYSTEM VALVE Service and Instrument: Air V72-38A/B, V72-89B/C, V72-103-Reactor Building Closed Cooling Water-V70-113, V70-117:
1:,
. Nuclear-Boiler V2-27A/B, V2-28A/B,- V2-39,jV2-40, V2-74,'V2-77, V2-80A-D, V2-86A-D, V2-96A/B Core. Spray V14-5A/B, V14-11A/B, V14-12A/B,-
. l.-
V14-13A/B, V14-26A/B
' High Pressure Coolant Injection V23-15,- V23-16, V23-25, V23-56, V23-62, V23-65, V23-842,s V23-843, SSC-23-12, SSC-23-13, Control Rod Drive V3-181,~V3-162A/B, V3-412A/B,.
V3-413A/B Residual Heat Removal V10-16A/B, V10-17, V10-18, V10-19A-D, V10-25A/B, V10-26A/B, V10-31A/B, V10-32, V10-33, V10-34A/B, V10-38A/B, V10-39A/B, V10-46A/B Reactor Core Isolation Cooling.
V13-15, V13-16, V23-27, V23-29, V13-38, V13-41, V13-50, SSC-13-9, SSC-13-10 Primary, Containment and Atmosphere SB16-19-6, SB16-19-6A/B Control SB16-19-7, SB16-19-7A/B, SB16-19-8, SB16-19-9, SB16-19-10, SB16-19-11A/B, V16-19-12A/B, V16-20-20, V16-20-22A/B, V16-19-23, V16-19-51, V16-19-52 l
Reactor Water Cleanup V12-15, V12-18, V12-68 Radwaste V20-82, V20-83, V20-94, V20-95 Containment Atmosphere FSO-109-75A1,2, Dilution FSO-109-75B1,2, FSO-109-75C1,2, FSO-75D1,2, VG-75A3,4, FSO-109-76A/B, VG-23, VG-34, l
VG-25, VG-26, VG-33, VG-34, l'
VG-9A/B, VG-22A/B, NG-11A/B, h
NG-12A/B, NG-13A/B
..TIP Ball A-C Rev. 10
.V-80
l NOTES 1.
A minimum of 1/2 of all safety valves shall be bersch-checked or replaced with a bench-checked valve each refueling outage. Both valves shall be i
checked or replaced every two refueling outages. The lift point of the safety valves shall be set as specified in Technical Specification Section 2.2.B.
I 2.
A minimum of 1/2 of all relief valves shall be bench-checked or replaced with a bench-checked valve each refueling outage. All four valves shall be checked or replaced every two refueling outages. The set pressures shall be as specified in Technical Specification Section 2.2.B.
l 3.
Prior to quarterly exercise and timing tests, decrease reactor power to less than 75 percent. At least twice a week, the MSIVs shall be exercised by partial closure and subsequent reopening.
4.
During each refueling outage, explode one of the three charges manufactured in the same batch to verify proper function.
Then install the untested charges in the explosion valves.
5.
Proper valve operation is shown both by the decrease in pump discharge pressure upon opening of valves V10-16A-0 and by proper automatic closing of V10-16A-D at approximately 2000 gpm.
6.
Valves are passive unless the pumpback system has operated during the cycle.
7.
Each refueling outage, each valve will be tested to determine the force l
required to open each valve from fully closed to fully open.
8.
Only one valve in each line is required to be operable per Tech. Spec. Table 4.7.2.b.
9.
Each refueling outage, each valve will be tested to verify that the setting is between 1400 and 1490 psig.
- 10. Valves V11-16 and V11-17 shall be leak tested each alternating refueling outage. Valve V10-18 shall be leak tested each refueling outage. Maximum leakage limit shall be 1.0 gpm at 101815 psid.
- 11. Valves V23-65 and V13-50 will also be disassembled and inspected at least once every 10 years.
(LER 87-18 and NRC Inspection Report 50-271/87-21).
{
- 12. Testing of V3-13-138 is not required when the corresponding control rod has been declared inoperable and its directional control valves disarmed per the provisions of Technical Specification 3.3.A.2.
Rev. 10 V-81
-. _ - _ _ - = _.
TABLE 1
,vJc In' addition to the allowable ranges establis'ed per:IWV-3417 and modified by relief h
request basis GV-2, the below quantitative values.are established based on the plant l
safety analysis'.. If these values can not be met the valve shall be declared-inopera-tive.
MAXIMUM CLOSING.
MAXIMUM OPENING VALVE' SYSTEM TIME (SEC)
TIME (SEC) l l
V70-117 RBCCW 45 V72-38A/B Service and Instrument Air 20 V2-39 Nuclear Boiler 5-(RA)'
V2-40 Nuclear Boiler 5 (RA)
V2-53A/B
' Nuclear Boiler 33
- V2-74 Nuclear Boiler
-35 V2-77 Nuclear Boiler 35 V2-80A-Dl Nuclear Boiler 5 **
V2-86A-D Nuclear Boiler 5 **
V14-11A/B Core Spray 8
8 V14-12A/B Core Spray.
8 8
V14-26A/B Core Spray 45 V23-14' HPCI 20.
20 V23-15 HPCI 55 V23-16 HPCI 55 V23-19 HPCI 20 20 V23-20 HPCI 20 20 V23-25 HPCI 10 10 V10-13A-D RHR 100 100 V10-17 RHR 28 V10-18 RHR 28 Rev. 10 V-82
1 M
.}.
i
. TABLE 1-(Cont.)
1 MAXIMUM CLOSING.
MAXIMUM OPENING
- VALVE SYSTEM TIME (SEC)
-TIME (SEC)
LV10-25A/B RHR-120 24 V10-26A/B RHR.
70 V10-27A/B' RHR 120 24-V10-31A/B ~
V10-33 RHR 25 LV10-34A/B RHR 120 V10-38A/B RHR 45 V10-39A/B RHR 70-V10 RHR.
25
~
V13-16' RCIC 20 V13-39 RCIC 30 V13-41 RCIC 30 SB16-19-6 PCAC 10 SB16-19-6A/B PCAC 10
'SB16-19-7 PCAC 10 ***
SB16-19-7A/B PCAC 10 ***
SB16-19-8 PCAC 10
'SB16-19-9 PCAC 10 5816-19-10 PCAC 10 SB16-19-23 PCAC 10 V20-82 RADWASTE 20
.Rev. 10 V-83
TABLE 1 (Cont.)
MAXIMUM CLOSING MAXIMUM OPENING VALVE' SYSTEM TIME (SEC)
TIME (SEC)
V20-83J RADWASTE 20 V20-94.
RADWASTE' 20 V20 RADWASTE' 20 V12-15 RWCU 25 V12-18
.RWCU 25 V12-68 RWCU 45 SGT-1A/B HVAC-Reactor Building 3
,SGT-2A/B-HVAC-Reactor Building' 3
i SGT-3A/B HVAC-Reactor Building 3
^SGT-4A/B' HVAC-Reactor Building 3
.SGT-5 HVAC-Reactor Building 3
HVAC-9 HVAC-Reactor Building 3
HVAC-10 HVAC-Reactor Building 3
HVAC-11 HVAC-Reactor Building 3
HVAC-12 HVAC-Reactor Building 3
FSC-109-76A/B CAD 5
(RA)
VG-23 CAD 5
(RA)
VG-26 CAD 5
(RA)
The closure time shall not be less than 27 seconds I
The closure time shall not be less than 3 seconds
- Valves SB16-19-7 and SB16-19-7A shall have stops installed to limit valve opening to 50* or less.
RA Rapid Acting Valves. A maximum limiting stroke time of 2 seconds is established.
l See Relief Request Basis Number RRB-GV-2.
Rev. 10 V-84 l
l'
h TABLE'2 VALVES IDENTIFIED FOR COLD SHUTDOWN EXERCISING DISCUSSION:
IWV-3412. permits valves to be exercised during cold shutdowns when exercising is not practical during plant operation. The ASME code further requires that these valves be specifically identified and full-stroke exercised during cold shutdowns. Since the requirements of the ASME code are being met, a relief.
request is not required. The below listing provides the required valve identi-fication.
Vermont Yankee differentiates, for valve testing purposes, between the cold shutdown mode and the refueling mode.
That is, for valves identified for-testing during cold shutdown, testing will be performed during both cold shut-downs and each refueling outage. For valves identified for testing during refueling outages, specific relief requests are provided in the IST Program and testing is performed only during each refueling outage.
TESTING GUIDELINES:
Cold shutdown testing of valves will be performed under the'following guidelines:
1.
Testing will commence as soon as practical after cold shutdown is achieved, but no later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after shutdown.
2.
Testing shall continue until either all testing is completed or the plant is. ready to return to operation. Completion of all valve testing is not a prerequisite to return to operation.
3.
Increases in valve testing frequency and required corrective actions prior to return to operation shall be in accordance with Relief Request Basis GV-1 and GV-2, respectively.
4.
Any testing not completed during one cold shutdown will be performed during any subsequent cold shutdowns starting from the last test per-formed at the previous cold shutdown.
5.
For planned shutdowns, where ample time is available and testing of all valves identified for the cold shutdown test frequency will be accomplished, exceptions to the 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> may be taken.
Rev. 10 l
l V-85
1 ec TABLE 2 (Cont.)
' SYSTEM VALVE' FUNCTION BASIS / ALTERNATE TESTING-RBCCW.
V70-113 RBCCW to Containment Valve is required"to be open-Check valve during power operation.
Shutting the valve would stop cooling water flow to vital containment equipment.
Valve will be verified to close during cold shutdowns and
+
refueling outages.
V70-117 RBCCW Return Valve cannot be exercised Isolation Valve during power operation since closing the valve would stop-cooling water flow to. vital containment equipment.
Valve will be full stroke exer-cised during. cold shutdowns and refueling outages.
' Nuclear Boiler.
SR2-14E-L Relief Valve Discharge Valves.cantsot be exercised Line Vacuum Breaker during power operation since valves are inside the drywell and are inaccessible when-at power.
Valves will be manually-exercised during cold shutdowns when the drywell is accessible and during refueling outages.
V2-53A/B-Recirculation Pump Valve exercising during power.
V2-54A/B Discharge and Bypass operation would require'a reac-Valves tor trip.
Valves will be full stroke exercised during cold shutdowns and refueling outages.
Core Spray V14-13A/B Injection Check Valves cannot be exercised Valves manually since valves _are located inside the primary con-tainment. Valves cannot be exercised with flow since pump discharge pressure cannot over-come reactor pressure.
These valves will be manually p
full stroke exercised during cold shutdowns when the drywell is accessible and during refueling outages.
R2v. 10 1V-86 l
.i' TABLE 2 (Cont.)
SYSTEM
' VALVE FUNCTION BASIS / ALTERNATE TESTING i
~HPCI V23-18 Injection Check Valve cannot be exercised i
Valve during power operation since I
flow through this valve must be !
injected into the reactor coolant system. This would thermally shock the reactor nozzles. The cold water injec-g tion would also cause a reac-tivity excursion. Manual valve operation is not possible during power. operation since the valve is located in the steam tunnel which is unac-cessible.
Valve will be manually fully l
stroke exercised during cold shutdowns and refueling outages.
V23-61 Torus Suction Valve cannot be full stroke Check Valve exercised during power opera-tion since there is no full flow test loop available to recirculate the water back to the torus. There are no means to manually stroke the valve.
Valve cannot be stroked via a system injection into the reac-tor since that would result in a reactivity excursion and potentially thermally shocking the reactor nozzles.
Valve will be verified to open freely and stroke fully during.
cold shutdowns and refuel outages.
RHR V10-17 Primary Containment Valves cannot be exercised V10-18 Isolation during power operation since there is a 100 psig interlock that prevents opening these valves during power operation.
]
Valves will be exercised during ;
cold shutdowns and refuel y
- outages, j
Rcv.-10 V-87 l
p,m b'
,i TABLE 2 (Cont'.)
- SYSTEM, VALVE FUNCTION BASIS / ALTERNATE TESTING V10-46A/B LPCI Injection Valves cannot be exercised Check Valves during power operation since the valves are located inside the primary containment.
Exercising the valves by system flow is not possible during power operation since pump
' discharge is unable to overcome reactor coolant system pressure.
Valves'will be manually full stroke exercised during cold-shutdowns when the drywell is accessible and during refueling-outages.
RCIC' V13-22 Injection Check Valve cannot'be exercised Valve during power operation since flow through this valve must be injected into the reactor coolant system. This would thermally shock the reactor nozzles. The cold water injec-tion would-also cause~a reac-tivity excursion.
Valve will be full stroke exer-cised during cold shutdowns and-refueling outages.
I J
Rav. 10 V-88
lt TABLE 2 (Cont.)
SYSTEM.
VALVE-FUNCTION BASIS / ALTERNATE TESTING V13-40' Torus Suction ~
Valve cannot be full stroke Check Valve exercised during power opera-
. tion since there is no full flow test loop available to recirculate the water back to the torus.- There are n6 means to manually stroke the valve.,
Valve cannot be stroked via a system injection into the.reac-tor since that would rsult in a.
. reactivity excursion.and poten-tially thermally shocking the.
reactor nozzles.
Valve will be verified to.open freely and stroke fully:during:
cold shutdowns and refuel outages.
PCAC SB16-19-8 Primary Containment Valves cannot be exercised V16-19-23 Isolation during power operation since this would cause the loss of the differential pressure bet-ween the drywell.and the suppression chamber.
This DP is a required condition of plant operation.
Valves will be full stroke exercised during cold shutdowns and refueling outages.
V16-19-12A/B Primary Containment Vacuum breaker cannot be exer-Isolation cised during power operation since there is no test loop available. There are no means to manually stroke the vacuum breaker.
During cold shutdowns and refueling outages, each vacuum breaker will be tested to determine that the force required to open the vacuum 7.
breaker does not exceed the F
force specified by Tech. Spec.
i Section 3.7.A.S.a and each F
vacuum breaker will be inspected and verified to meet the design requirements.
.R3v. 10' L
V-89 l
TABLE 2 (Cont.)
J-<
SYSTEM VALVE
. FUNCTION BASIS / ALTERNATE TESTING-
.CRD V3-181 Primary containment
. Valve cannot be exercised Isolation during power operation since this would require isolating and venting a. portion of the CRD system. This would cause-hydraulic instability throughout the system..This situation is potentially unsafe' until.the system can be re-balanced-and the rod strokes
.retimed. This cannot be done during power' operation.
Valve is. verified'open during normal system operation. During cold shutdown and. refueling
. outages, the valve will be verified to close.
- S:rvice and-V72-898/C Primary Containment Valve cannot be exercised-Instrument Air Isolation during power operation since closing the valve could cause the air. operated main steam isolation valves to close, resulting in a reactor scram.
Valve is verified open during normal system operation. During cold shutdown and refueling outages,.the valve will be verified to close.
4 c
- Rrv. 10' V-90 l-
_ _ - _ - _ _ _ _ _ _ - _ - _ _ - _ _