ML20235K365
| ML20235K365 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/30/1987 |
| From: | Mcdonald R ALABAMA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8710050060 | |
| Download: ML20235K365 (196) | |
Text
_ - - - _.
s Alabama Power Company GOO North 18th Street Post Office Box 2641 Birmingham, Mabama 35291-0400 Telephone 205 250-1835 L
R. P. Mcdonald Alabama Power Sonior Vice President the southem electnc system 10CFR50.55a(g)
September 30, 1987 Docket No. 50-348 U. S. Nuclear Regulatory Commission ATTN: Dccum' " Control Desk Washington
. C. 20555 Gentlemen:
Joseph M. Farley Nuclear Plant - Unit 1 Second Ten Year Internal Inservice Testing Program for ASME Code Class 1, 2 and 3 Pumps and Valves By letter dated May 27, 1987, Alabama Power Company submitted the Inservice Testing (IST) Program for the Second Ten Year Interval of Unit 1 operation.
Following an initial review by the NRC, a meeting was held at Farley Nuclear Plant on August 25 and 26, 1987 to discuss the IST Program review and resolve remaining open issues. As a result of this meeting, the IST Program has been revised and is herewith submitted as Enclosure 1 for final NRC review. This program supersedes the program previously submitted by the May 27, 1987 letter.
In addition to the revised IST Program, the NRC also requested that additional information be submitted in several areas. A listing of this information and a brief discussion of each item follows:
1.
Relief Request Correlation List - The NRC requested a listing correlating the First Ten Year Interval IST Program relief requests and corresponding NRC SER dates to the Second Ten Year Interval IST Program relief requests. The reliefs granted by the NRC during the First Ten Year Interval which are shown in this list are essentially the same as the corresponding reliefs requested for the Second Ten Yaar Interval. This list is provided as Enclosure 2.
2.
Valve Stroke Time List - A list of the limiting values of full stroke time for all power operated valves in the IST Program will be submitted by October 31, 1987 for NRC review.
This list is being submitted for information purposes only and will not be incorporated into the IST Program. The valve stroke times are subject to change during the life of the plant and will be revised in plant procedures and test plans accordingly.
8710050060 870930 g (
p l
E-._ __
e U. S. Nuclear Regulatory Commission September 30, 1987 Page 2 3.
High and Low Head Safety injection System Check Valve Tests - During the meeting, the NRC requested an additional technical justification supporting Alabama Power Company's. position that the Safety Injection / Loss-of-Off Site Power (SI/LOSP) Test performed during refueling outages would individually verify the full stroke
. exercising of each check valve in the High Head Safety Injection (HHSI) and Low Head Safety Injection (LHSI) systems. At Alabama i
Power Company's request, Westinghouse evaluated the SI/LOSP test procedure and the failure history of the valves in question and determined that the existing test provides adequate assurance that the check valves will perform properly. A copy of the Westinghouse evaluation is provided as Enclosure 3.
4.
River Water System Pumps and Valves - For administrative purposes, Alabama Power Company included the River Water System pumps and valves in the augmented portion of the IST Program previously submitted as a means of ensuring system reliability. Since the augmented portion of the IST Program has been deleted at the NRC's request and the River Water System is not needed for safe shutdown of the plant, these pumps and valves were deleted. Amendment 45 to the Unit 1 Technical Specifications deleted the River Water System and the technical basis supporting this amendment fully justifies safe plant shutdown without use of the River Water System.
Since the information provided herein supersedes that previcusly submitted by the May 27, 1987 letter, no additional application fees are required.
It is respectfully requested that the relief requests included in Enclosure 1 be granted by December 1,1987.
If there are any questions, please advise.
Respectfully str itted, ALABAMA P W R C0 ANY
/
(
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{('l./ trV f
f i
R. P. Mcdonald RPM / STB: dst-D70 Enclosures cc: Mr. L. B. Long - w/o enclosure Dr. J. N. Grace - w/1 enclosure Mr. E. A. Reeves - w/1 enclosure Mr. W. H. Bradford - w/o enclosure
l ENCLOSURE 1
FNP-1-M-042 Rev. O O
ALABAMA POWER COMPANY JOSEPH M. FARLEY NUCLEAR PLANT SECOND 10-YEAR PUMP AND VALVE INSERVICE TESTING PROGRAM l
OF THE l
l JOSEPH M. FARLEY UNIT NO. 1 l
NUCLEAR GENERATING PLANT
(
ASHFORD, ALABAMA 36312 FOR ALABAMA POWER COMPANY 600 NORTH 18th STREET BIRMINGHAM, ALABAMA 35202 COMMERCIAL SERVICE DATE:
12-01-77 Operating Capacity:
829 MWe APPROVAL:
Date Issued:
General Manager-Nuclear Plant t
O l
04011
)
I FNP-1-M-042
~
e '.
FNP UNIT 1
-PUMP AND VALVE INSERVICE TESTING PROGRAM j
TABLE OF CONTENTS S_ection Title Page I
INTRODUCTION i
I.1 General I~-1 I.2-Definitions I-1 I.3 General Relief Requests for Pumps I-2 I.4.
General Relief Requests for Valves I-3 i
II PUMP IST PROGRAM II.1 Introduction II-1 II.2 Pump IST Program Concept II-1 II.3 Pump List II-1 II.4 Pump Test List. Nomenclature II-2 II.5 :
Pump Test List and Relief Requests for ASME Class 1, 2, and 3 Pumps Residual Heat Removal (RHR)
II-1-1 Containment Spray (CS)
II-1-2 HHSI/CVCS II-1-3
("N Boric Acid Transfer /CVCS II-1-4
\\.-
II-1-5 Service Water (SW)
II-1-6 Component Cooling Water (CCW)
II-1-7 Diesel Generator Fuel Oil Transfer II-1-8 Pump Test List Notes-ASME Class 1,2 and 3 II-1-9 Pump Relief Requests II-1-10 III VALVE IST PROGRAM III.1 Introduction III-1 III.2 Valve IST Program Concept III-1 III.3 Valve Test List Nomenclature III-2 III.4 Drawing List III-5 III.5 :
Valve Test Lists and Relief Requests for ASME Class 1, 2, and Valves Reactor Coolant (B13)
III-1-1-1 LHSI/RER (Ell)
III-1-2-1 Reactor Cavity Cooling (E12)
III-1-3-1 Containment Spray (E13)
III-1-4-1 Containment Isolation (E14)
III-1-5-1 Penetration Room Filtration (E15)
III-1-6-1 l
(Z) j i
0401I i
REV. 0
l
.FNP-1-M-042 1,
FNP UNIT 1 TABLE'OF CONTENTS (CONT)
Section~
Title Page SI/CVCS-L(E21)
III-1-7-1
< Reactor Cavity Post-LOCA Dilution (E22)
III-1-8-1 Post Accident Containment Vent and Sample III-1-9 (E23)
Liquid Waste Disposal (G21)
III-1-10-1 Steam Generator Blowdown (G24)
III-1-11-1 Spent. Fuel Pool Cooling (G31)
III-1-12-1
-Main Steam (N11)
III-1-13-1 Auxiliary Steam (N12)
-III-1-14-1 Feedwater (N21/C22):
III-1-15-1 Auxiliary Feedwater (N23)
III-1-16-1 Chemical Injection (N25)
III-1-17-1 Demineralized Water (P11)
III-1-18-11 Containment Purge (P13)
III-1-19-1 Sampling (P15)
III-1-20-1
' Service. Water (P16)
III-1-21-1 Component Cooling Water (P17)
III-1-22-1 Se.:vice: Air (P18)
III-1-23-1 Instrument Air-(P19)
III-1-24-1
-(
Containment Ccoling and Purge (P23)
III-1-25-1 1:
Diesel Generator Air Start (R43)
III-1-26-1 Non-Radioactive Vent (V47)
III-1-27-1 Spent Fuel Fool Vent and Filtration (V48)
III-1-28-1 Control Room HVAC and Filtration (V49)
III-1-29-1 Diesel Genrator Fuel Oil Transfer (YS2)
III-1-30-1 0401I 11 REV. O
FNP-1-M-042 O
l l
PUMP AND VALVE INSERVICE TESTING PROGRAM I
l FOR FARLEY NUCLEAR PLANT l
l 1
UNIT 1 SECTION I INTRODUCTION O
O 03961 REV. O
[
FNP-1-M-042 l
(
):
I.
INTRODUCTION I.1
' GENERAL This-document presents the' program for inservice testing (IST) of' pumps and valves at Unit 1 of the Farley-Nuclear Plant (FNP) in compliance-with the requirements of 10 CFR 50.55a.
According to.10 CFR 50.55a(g)(4)(ii),.following completion of the first 120-month inspection interval, successive 120-month inspection intervals shall comply with the requirements of the latest edition and addenda of the American Society of Mechanical Engineers (ASME) Code incorporated by reference in paragraph (b) of 10 CFR 50.55a 12 months prior to the start of the 120-month inspection interval.
The second 120-month inspection interval for Farley Unit 1 will commence on December 1, 1987.
Based upon this date, the Farley Unit 1 IST program for the second 120-month inspection interval is in compliance with the requirements of Section XI of the ASME_ Boiler and Pressure Vessel Code, 1983' Edition with Addenda through Summer 1983.
I.2 DEFINITIONS The terms below, when used in the Inservice Testing Program, are defined as follows.
()
Quarterly:
An interval of 92 days for Lesting components which can be tested during normal plant operation.
Cold _ Shutdown:
Testing delayed until cold shutdown will commence as soon as cold shutdown condition 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 achieving cold shutdown.
Testing will continue until all tests are complete or the plant is ready to return to power.
Completion of testing is not a prerequisite to return to power, and any testing not completed at one cold shutdown will be performed during subsequent cold shutdowns before the refueling outage.
No cold shutdown testing will be performed on any components tested less than 92 days prior to achieving cold shutdown.
The 48-hour interval will not hold for planned cold shutdowns where all required testing will be completed.
In addition, all components which have testing delayed to cold shutdown will be tested during each refueling unless the O
component has been tested during the previous three months.
i 0396I I-1 REV. O
FNP-1-M-042 Refueling:
Testing delayed to refueling will be (c x'^)
performed during the normal scheduled refueling shutdown before. returning to power. operation.
Period:
Category C safety and relief valves (IWV-3511), Category D explosive actuated valves (IWV-3610), and Category D rupture disks (IWV-3620) are periodically tested, as defined in the appropriate Code sections.
Pressure Isolation:
Any valve which acts a-La isolation boundary between the high-pressure reactor coolant system and a system l
having a lower operating or design
}
pressure.
Containment Isolation:
Any valve which performs a containment isolation function and is included in the Appendix J, Type C, local leak rate test program.
Active:
Any valve which is required to change position to accomplish its safety-related function.
Passive:
Any valve which is not required to change position to accomplish a specific function and for which the Code does not require operability testing.
I.3 GENERAL RELIEF REQUESTS FOR PUMPS This section requests relief from specific requirements of Section XI found to be impractical for this site.
Since they are general in nature and pertain to a number of components, this section requests general relief as presented below.
General Relief Request:
None O
0396I I-2 REV. O
1 L
I FNP-1-M-042 I.4 GENERAL RELIEF REQUESTS FOR VALVES ih
(/
I This section requests relief from specific requirements of Section XI found to be impractical for this site.
Since they-are general in nature and pertain to a number of components, i
l this section requests general relief as presented below:
General Relief Request:
VG-1 Components:
Rapid actuating power-operated valves I
with stroke times of 2 seconds or less.
l l
Category:
A, B Code Requirements:
IWV-3417 requires corrective action if the measured stroke time for a valve i
which normally strokes in 10 seconds or less increases by 50 percent from the L
last measured stroke time.
IWV-3413 requires measurement to the nearest second for stroke times of 10 seconds or less.
Basis for Relief:
For rapid actuating power-operated valves, the application of the above
/'_T criteria could result in requiring
't /
corrective action when the valves are functioning normally.
These valves are generally small air and solenoid-operated valves which, because of their size and actuator types, stroke very quickly.
Operating history on this type of valve indicates that they generally either operate immediately or fail to operate in a reasonable length of time.
The intent of the referenced Code sections is to track valve stroke time as a means of detecting valve degradation.
This type of valve does not lend itself to this tracking technique.
Alternate Testing:
A maximum stroke time of 2 seconds will be specified for each rapid actuating valve.
If the measured valve stroke time is 2 seconds or less, it will be considered as acceptable, and no corrective action will be required.
If the measured valve stroke time exceeds 2 seconds, it will be considered inoperable, and appropriate corrective g()
action will be taken.
03961 I-3 REV. O
' b:
1 L L j
FNP-1-M-042;
]
t,),.
GeneralLRelief i
fs Request:
VG-2.
Components:
Valves tested at cold shutdown.
Category:
A, B, C l
Code Requirements:
.IWV-3417' states that when corrective action is required as a result of tests i
made during cold shutdown,Ethe condition-shall.be corrected before startup.
A i
retest showing acceptable operation shall be run following any required corrective action before the' valve is returned to service, 1
Basis for Relief:
The plant Technical Specifications provide'the requirements and plant conditions necessary for plant startup.
and mode changes.
-)
' Alternate Testing:
The test requirement will be satisfied before the valve is required for plant operability, as defined in the plant'
]
_ Technical Specifications.
l
)
(
General Relief Request:
VG-3 Component:
Containment Isolation Valves Code Requirements:
Articles IWV-3421 through IWV-3425 require valve leak rate tesing for each Category A valve in the Inservice Test Program.
Category:
A, AC Basis for Relief:
Containment isolation valves which are designated as Category A or AC are leak rate tested to the requirements of Appendix J to 10 CFR 50.
Appendix J, Type C, valve local leak rate test procedures and requirements fulfill the intent of Articles IWV-3421 through IWV-3425.
1 j
O.
0396I I-4 REV. 0
FNP-1-M-042 3
rx Alternate Testing:
Containment isolation valves will be
' _)
local leak rate tested to the s
requirements of Appendix J, Type C testing in lieu of those required by Articles IWV-3420 through IWV-3426.
The analysis of leakage rates and corrective action requirements of Articles IWV-3426 and IWV-3427 will be performed.
General Relief Request:
VG-4 Component:
Pressure Isolation Valves Code Requirements:
For Section XI Category A valves, IWV-3426 requires comparison of measured leakage rates with previous measured leakage rates.
Category:
A, AC Basis for Relief:
Technical Specification Section 3.4.7.2 defines the limiting conditions for operations and Section,4.4.7.2.2 defines the surveillance requirements for
(}
pressure isolation valves as follows:
"Each reactor coolant system pressure isolation valve specified in Table 3.4-1 shall be demonstrated operable pursuant to Specification 4.0.5 except that in lieu of any leakage testing required by Specification 4.0.5, each valve should be demonstrated operable by verifying leakage to be within the allowable leakage critera of 0.5 gpm per inch of nominal valve size with an upper limit of the maximum allowable leakage in Table 3.4-1; and the measured leak rate for any given test cannot reduce the difference between the results of the previous test and the maximum allowable leakage specified in Table 3.4-1 by more than 50%:
l l
1 1
0396I I-5 REV. O l
I
m.__-_
FNP-1-M-042-a.
.Every refueling outage during UI h i
-startup.
l N f' b.
. Prior.to returning the valve.to service.following maintenance, repair or replacement work on the-
~
valve affecting.the-seating
. capability.of the valve.
~
c.
'Following valve-actuation due to automatic or manual' action or flow through the valve for valves identified in Table 3.4-1 by an asterisk.
d.
'The provisions of Specification 4.0.4 are not applicable for entry into mode 3:or 4."
i,lternate Testing:
The. Technical Specification-defined surveillance testing.will be performed, but no comparison of test results to previous:results will be performed.
O 4
0396I I-6 REV. O
.t' FNP-1-M-042 (e
b#
1 PUMP AND VALVE INSERVICE TESTING PROGRAM FOR
\\
FARLEY NUCLEAR PLANT UNIT 1 SECTION II PUMP IST PROGRAM i% -
U O
i 0387I REV. 0
---_________________D
FNP-1-M-042
.r-II.
PUMP IST PROGRAM d
l II.1 INTRODUCTION This section presents the program for inservice testing (IST) of I
safety-related' pumps at Unit 1 of the Farley Nuclear Plant, in compliance with the requirements of 10 CFR 50.55a.
This program has been prepared to-the requirements of the American Society of Mechanical Engineers-(ASME) Boiler and Pressure Vessel Code,Section XI,. Subsection IWP, 1983 Edition with Addenda through j
Summer 1983,.for ASME Class 1, 2, and 3' pumps which are provided
-with an emergency power source and perform a specific function in shutting down the reactor or mitigating the consequences of 1
an accident.
)
1 II.2 PUMP IST PROGRAM CONCEPT i
i to this~section addresses Section Kl' testing I
requirements for all ASME Class 1, 2, and 3 pumps provided with an emergency power source, and which are required to' perform a specific function in shutting down the reactor or mitigating the l
consequences of an accident.
Test requirements determined to be impractical for a large number of pumps have been addressed in Section I under General Relief Requests for Pumps.
In addition rfT to those general relief requests, this section includes requests
(_/
for relief from Code requirements found to be impractical for I
. specific pumps.
Each relief request provides justification for deviation from the Section XI specified test and proposes appropriate alternate testing.
l l
i II.3 PUMP LIST i
i Pumps included in this program are as follows:
]
l ASME Class 1, 2,
and 3 Pumps
]
l P&ID Drawing Boundary No. of System No.
Drawing No.
Pumps Residual heat removal D-175041 D-351118 2
Containment spray D-175038/3 D-351115/3 2
Safety injection /CVCS D-175039/2-D-351116/2 3
Boric acid transfer /CVCS D-175039/3 D-351116/3 2
Auxiliary feedwater D-175007 D-351106 3
l Service water D-170119/1 D-351130/1 5
l Component cooling water D-175002/1 D-351103/1 3
L Diesel generator D-170060 D-351132 8
fuel oil transfer 0387I II-1 REV. O
r-_
FNP-1-M-042 II'.4 PUMP TEST' LIST NOMENCLATURE Legend For Headings Pump'I.D. No.
- Unique: pump identification number..
ISI Class The classification as determined for Section'XI.
Dwg/ sheet Number
- Piping and Instrumentation' diagram and boundary diagram on which pump is shown.
Coordinates
- Location on drawing where pump in shown.
i.
Pump Descriptions
- Functional name of pump.
I Relief Request
- Applicable relief request numbers are indicated with a "PR" prefix.
. Notes
- Notes are located behind the last Pump Test List.
Legend For Pump Parameters Pi - Inlet pressure (psig)
Po - Outlet pressure (psig) dP - Differential pressure:
dP = P -P (psi) g Q
- Flowrate (gal / min)
O,-
L V
- Vibration amplitude (mil)
T
- Bearing temperature ( F)
LL - Lubricant level or pressure (NA)
N
- Speed (rpm)
PR - Pump relief request Legend for Frequency of Test l
Q
- Quarterly CS
- Cold shutdown R
- Refueling A
- Annually N/A - Not applicable
- Test deleted, see Relief Request.
O 0387I II-2 REV,. 0
l T
- 1.
FNP-1-M-042
' '~
/
1
' PUMPAND VALVE INSERVICE' TESTING, PROGRAM'
~
I FOR FARLEY NUCLEAR PLANT-f UNIT 1 e
SECTION II II.5 ATTACHMENT-1:
PUMP TEST LIST AND RELIEF REQUESTS FOR ASME CLASS 1,'2, AND 3 PUMPS t
O 0387I REV. O
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7 FNP-1-M-042 j
i 1
PUMP TEST LIST NOTES ASME Class 1,2, and 3 The-Pump. Test List identifies the test parameters to be measured or observed, and the test frequencies.
Notes 1 through 6 refer to' amplifications of the Code requirements and are further discussed below:
l.
on a pump with constant speed drive, speed is not measured, since the test will be performed at-nominal motor nameplate speed:as, required by Section XI, IWP-3100.
2.
Quarterly tssting of the containment spray pumps is performed using pump recirculation flow through a small-diameter recirculation line.
_A full-flow test will be performed at refueling by installing spool pieces and performing a full-flow test through the test line to the containment refueling cavity.
3.
Inlet pressure is to be calculated from the. inlet liquid i
level.
l
- 4.
Bearing temperature measurement is not required (IWP'-4310),
since bearings are in the pumped fluid flow path, such that they are completely. immersed in and lubricated by the pumped fluid.
5, Pump lubricant level or pressure is not observed because of bearing lubrication design.- Pump motor lubrication is observed in lieu of pump lubricant level or pressure.
6.
Flow rate will be measured during diesel generator testing
]
by. measuring increase in day tank level versus time when the q
transfer pumps are in operation.
Duration of test will be limited to the time it takes to replenish day tank level.
l i
'O 0387I II-1-9
.REV. O L
i FNP-1-M-042 l
PUMP, RELIEF REQUEST j
G l
l -
PR-1
~
i System:
All'(except Service Water and Diesel Generator fuel oil transfer).
]
Pump:.
All-(except Service Water and Diesel Generator fuel' oil transfer).
Class:
2,3 i
Function:
Various Test Requirement
- Measure pump bearing temperature J
(IWP-4300).
Basis,for Relief:
These pumps have no installed instrumentation which measures bearing temperature.
Measurement of temperature of the pump bearing housing would not be 3
indicative of actual bearing temperature 1
because of temperature gradients caused by operation of space coolers, pump location, pumped fluid, etc.
The
/*
once/ year measurement will not provide significant information relative to pump condition.
The. extended pump running time required to. achieve temperature stability could result in unnecessary wear on the pumps and result in increased pump maintenance and repair.
Deletion of this measurement will not have significant affect on the pump monitoring program, since other required test parameters are being measured.
Alternate Testing:
Pump differential pressure, flow, and vibration (as applicable) will be used to monitor pump performance.
O 0387I II-1-lO REV. O
$31 FNF;1-M-042'
/-
PUMP RELIEF. REQUEST
. '\\
L p,
System:
-Pumps.
POO1A-A, P001B-B' Class:
2 Function:
Low-head. safety injection and residual heat removal from the reactor coolant system.
Test Requirement:
IWP-4120 requires that the' full-scale range of-each instrument be no more than
'three times the reference'value.
Basis for Relief:
Reference values for suction pressures for these pumps is between 48 and 54 l
psig.
This would require suction pressure gauges of 0-150,psig maximum.
.The-accuracy required for these-gauges l
would be 2. percent of 150 psig, which is
+3.0 psig.
The installed pump inlet l
pressure gauges are 0-200.psig.
l I
k-Although the installed instruments are i
above the maximum range limits, they are within the accuracy requirements and are therefore adequate for pump testing.
Alternate Testing:
The installed instruments will be used
{
i for taking inlet' pressure measurements during pump testing.
l l
(%
%.)
1 L
0387I II-1-11 REV. O l
l FNP-1-M-042 PUMP RELIEF REQUEST
(_)/
PR-3 j
i l
System:
)
Pump:
POO1A-A, P001B-B Class:
2 Function:
To reduce containment pressure and airborne fission product removal from the post-LOCA containment atmosphere.
Test Requirement:
IWP-3100 requires that each measured test quantity be compared to the reference value of the same quantity.
Any deviation determined shall be compared to the limits given in Table IWP-3100-2.
Basis for Relief:
Section XI pump testing is performed by either varying the system resistance until either the measured differential pressure or the measured flow rate
(~J equals the corresponding reference N
k-value, or by using a' fixed resistance test flow path.
Testing the containment spray pumps by varying system resistance is not a practical method because to do so would inject a large quantity of water into the containment atmosphere.
The only possible fixed resistance pump test flow path is the small 2-1 ch pump recirculation line back to the refueling water storage tank.
The intent of Code required pump test data is to detect pump hydraulic degradation as indicated by small changes in the test measurements at a repeatable reference point on the pump head capacity curve.
Deviation from the reference value can be an indication of either pump degradation or a change in system resistance.
Use of the minimum flow line restricts flow rate to approximately 150 gpm and establishes the test reference point on the essentially flat portion of the head capacity curve.
At this reference point 7-s the Code acceptable range for
(_)
differential pressure corresponds to a 0387I II-1-12 REV. O
FNP-1-M-042-PUMP RELIEF REQUEST 1
il
_~
PR-3'(cont.)
l Basis for Relief:-
flow rate range from 0;gpm toL (continued) approximately 15 times the reference value.
Under these1 test conditions pump test flow rate deviation from the reference value is primarily.a. function of change in the test flow path resistance.
Any small change in the test flow path from erosion, corrosion, temperature variations, etc., will translate to a:large percentage.
variation from the reference value.
Consequently, flow rate measurement would not provide any useful information to monitor pump operability or.
degradation. -Because of this,.the
. recirculation line flow rate will be measured during. quarterly pump testing as a'means.of. detecting gross pump degradation, but the limits of Table IWP-3100-2 will not be applied to the test data.
< (/
Alternate.Testingt
-Pump differential pressure and vibration measurements will be-used to evaluate pump performance.
().
0387I II-1-13 REV. 0
FNP-1-M-042 g..;
PUMP RELIEF REQUEST (C~
PR-4 System:
HHSI/CVCS Pump:.
P002A, P002B, P002C-B
- function:
. Normal' chemical and volume control' system charging water and high-head safety injection (HHSI) to the reactor coolant system (RCS).
Tset Requirement:
IWP-3100 requires.that each measured test quantity be compared to the reference value of the same quantity.
Any deviation determined shall be compared to~the limits given in Table IWP-3100-2.
Basis for Relief:
Section XI pump testing is performed by either' varying the system resistance until either the measured differential
, pressure cnr the measured flow rate equals the corresponding reference j'
value, or by using a fixed resistance e
test flow path.
One:of the HHSI/CVCS pumps is aligned to provide normal charging and seal water flow while the pump being tested is aligned to fixed resistance minimum flow line.
The a
intent of Code required pump test data is to detect pump hydraulic degradation as indicated by small changes in the test measurements at a repeatable reference point on the pump head capacity curve.
Deviation from the reference value can be an indication of either pump degradation or a change in system resistance.
Use of the minimum flow line restricts flow rate to approximately 60 gpm and establishes the reference point on the essentially flat portion of the head capacity curve.
At this reference point the Code acceptable range for differential pressure corresponds to a flow rate range from O gpm to approximately 5 times the reference value.
Under these test conditions pump test flow rate deviation 0
0387I II-1-14 REV. O l
FNP-1-M-042 PUMP RELIEF REQUEST O
PR-4 (cont.)
Basis for Relief:
from the reference value is primarily a (continued) function of change in the test flow path resistance.
Any small change in the test flow path from erosion, corrosion, temperature variations, etc., will translate to a large percentage variation from the reference value.
l Because of this, flow rate measurement would not provide any useful information l
to monitor pump operability or degradation.
Alternate Testing:
Pump differential pressure and vibration measurements will be used to evaluate pump performance.
O e
O 0387I II-1-15 REV. O
i i
i FNP-1-M-042 i
i
)
r3 PUMP RELIEF REQUEST l
\\_)
l PR-5 I
J System:
HHSI/CVCS Pump:
. Class:
2 Function Normal chemical and volume control system charging water and HHSI to the RCS.
Test Requirement:
IWP-4120 requires that the full-scale range of each instrument be no more than three times the reference value.
Basis for Relief:
Reference values for suction pressures for these pumps are between 25 and 35 psig.
This would require suction pressure gauges of 0-75 p,sig maximum.
The accuracy required for these gauges would be 2 percent of 75 psig, which is 11.5 psig.
The installed pump inlet
(\\
pressure gauges are 0-100 psig il psig.
Although the installed instruments are above the maximum range limits, they are within the accuracy requirements and are therfore adequate for pump testing.
Alternate Testing:
The installed instruments will be used for taking inlet pressure measurements i
during pump testing.
1 i
l
~s t
0387I II-1-16 REV. O
i-
[;
_ M, FNP-1-M-042.
'A PUMP RELIEF REQUEST PR-6
.r Systems.
~CVCS Boric Acid Transfer-Pump:
P005A-A, POO5B-B class:
-3 Function:
Transfer of concentrated boric acid from-the boric acid tanks to the chemical and l
volume control system (CVCS).
Test Requirement:
. Quarterly measurement'of pump flow ~ rate.
Basis for Relief Quarterly pump testing is performed using the orificed. pump. discharge. test line which runs back to the boric acid storage. tank.
This.line does not'have any installed flow-measuring instrumentation.
To utilize the-system flow meter would require a test' flow path which would transfer highly concentrated boric acid'from the boric
. ( ).-
acid tank into.the CVCS and into the RCS through the operating CVCS charging pump.
The addition of concentrated boric acid to the RCS during normal operations would adversely affect the boric acid concentration in the RCS and' could cause a forced plant shutdown.
Alternate Testing:
Pump flow rate will be measured during boric acid transfer pump operation for borating the RCS for entering cold shutdown.
4 O
0387I II-1-17 REV. 0
FNP-1-M-042 PUMP RELIEF REQUEST PR-7 System:
CVCS Boric Acid Transfer Pump:
3 Function:
Transfer of concentrated boric acid from the boric acid tanks to the (CVCS).
Test Requirement:
IWP-4120 requires that the full-scale range of each instrument be no more than three times the reference value.
Basis for Relief:
Pump test flow rates are measured during boric acid transfer pump operation for borating the RCS for entering cold shutdown.
The only flow rate instrumentation in the test path is Q1E21FI110.
This is a 0-200 gpm full-scale flow element which is designed to monitor maximum system O^
operating conditions.
Because of shutdown procedure restrictions, the maximum pump test flow rate is limited to 30 gpm.
The flow element is within the accuracy requirements of Table IWP-4110-1.
The difference between the Code range and the range of the installed instrument should have no significant effect on the adequacy of the measurement.
Alternate Testing:
The installed flow element will be useo for taking flow rate measurements during pump testing.
O 0387I II-1-18 REV. O
i.r FNP-1-M-042-i f4 =
PUMP-RELIEF REQUEST 3
' (/..
PR-8 System:
Auxiliary Feedwater Pump:
3 Function:'
Provide auxiliary'feedwater to the steam generators on loss of main feedwater.
Provide feedwater to the steam generators during startup and shutdown.
. Test Requirement:
IWP-3100 requires that each measured' test quantity be compared to the refarence value of the same quantity.
Any deviation determined shall be compared.to the limits given in Table IWP-3100-2.
Basis for Relief:
Section XI pump testing is performed by
.either varying the system resistance until either the measured differential
~T
(/
pressure or the measured-flow rate
\\-
equals the corresponding reference i
value, or by using a fixed resistance j
test flow path... Testing the auxiliary
]
feedwater pumps by varying system resistance is not a practical method because to do so would inject cold water
)
into the steam generators.
The introduction of cold water into the hot j
steam generator would result in a large thermal shock and could result in nozzle cracking.
The only possible fixed resistance pump test flow paths are the pump minimum flow tines.
The intent of Code required pump test data is to detect pump hydraulic degradation as indicated by small changes in the test measurement at a repeatable reference
)
point on the pump head capacity curve.
1 Devittion from the reference value can l
be an indication of either pump degradation or a change in system resistance.
Use of the minimum flow line restricts flow rate to approximately 50 gpm and establishes the test reference point on the essentially
(
flat portion of the head capacity curve.
At this reference point the Code 0387I II-1-19 REV. O
1
-'i u
i FNP-1-M-042 J
.1 V:
PUMP: RELIEF REQUEST c
U',
PR-8. ( cont. '..)
- Basis for Relief:-
. acceptable range.for differential l(continued).
pressure corresponds'tc.a flow = rate.
i d
range from 0 gpm to approximately.2 times the reference value.
Under these
' test conditions pump' test' flow rate deviation from;the reference.value-is primarily a function of change in the test flow. path resistance - Any small' change-in the test flow path from erosion, corrosion, temperature
. variations, etc.', will translate to a 11arge percentage variation from the reference value, Becauce'of this, flow rate measurement would not provide any useful'information.to monitor pump
~
o'perability or degradation.
. Alternate Testing:
Pump. differential pressure and vibration
. measurements will be used to evaluate pump performance.
O 1
O 0387I II-1-20 REV. O
t 1
< wJ FNP-1-M-042 gr PUMP' RELIEF REQUEST PR-9.
J.
Systems-Auxiliary Feedwater Pumps.
'P001A-A, P001B-B, P002 Class:
2
- Function Provide auxiliary feedwater to the steam generators on loss'of main feedwater.
Provide feedwater to the steam generators during startup and shutdown.
Test Requirements:.
IWP-4120 requires that.the; full-scale range of each instrument be no more than three times the reference value.
' Basis for Relief:
Reference values for suction pressures for these' pumps are between 30 and 40.
psig..This would requir, suction pressure gauges of 0-90 psig maximum.
The' accuracy required for these gauges
!I*--
would be,2 percent of.90 psig,-which is 11.8 psig.
The installed pump. inlet j
pressure gauges are 0-100 12 psig.
l Although the installed instruments are above the maximum range limits, they are essentially equal'to the.kfore adequate accuracy L
requirements and'are ther for' pump testing.
Alternate Testing:
The installed instruments will be used for taking inlet pressure measurements during pump testing.
i 0
0387I II-1-21 REV. O
FNP-1-M-042 PUMP RELIEF REQUEST s
PR-10 System:
Service Water Pump:
P001A-A, P001B-A, P001C-AB, P001D-B, POOlE-B Class:
3 Function:
Provide cooling water to safety-related equipment.
l Test Requirement:
IWP-3400(a) requires that an inservice test be run on each pump.
Basis for Relief:
Due to the demands of dependent systems, the individual testing of service water pumps, as required by IWP-3400, would jeopardize safe plant operation and be impossible to accomplish during plant shutdown.
Alternate Testing:
Tests involving combinations of two
'/T pumps within each train will indicate
(_/
the hydraulic condition of the pumping system.
The combinations are arranged such that each pump is included in at least one combination test in each train.
The test results are applied to both pumps in the combir.ation.
0387I II-1-22 REV. O
l l
FNP-1-M"042-
~
b L
PUMP RELIEF, REQUEST
^
li f 5
.PR-ll System:
- Pump:
P001A-A,'P001B-A, P001C-AB,'P001D-B, P001E-B Class:
3 Function:
Provide cooling water to safety-related
~
. equipment.
' Test Requirement:
IWP-3100-2 specifies acceptable, alert, and required action ranges.for high flow.
relative to baseline. flow on an
.individualipump basis.
L, Basis for Relief:
Service water pumps must be run in two 1
pump combinations to meet safe plant L,
operation requirements (see Pump Relief ~
l Request PR-10).
The acceptable, alert, and required action ranges'of IWP-3100, however,.are based on individual' pump flows.
Since a high relative flow does L ",
not indicate pump degradation, the high' flow ranges may be expanded'to incorporate two pump operation without jeopardizing service water. reliability.
' Alternate Testing:
A test' parameter of flow-(Q) will be l
measured for each train (two pumps operating in each train).
The swing pump will be operated with either of the
. pumps in the train to which it is aligned, and flow will be measured for the train.
The following high ranges will be used to evaluate each two pump combination.
I-Acceptable Q<l.04 Qr q
Alert 1.04Q sQ<l.06 Q r
r I
Required Action Q>l.06 Qr If a pump-combination-total flow falls in the alert or required action ranges each of the pumps is then tested in combination with another appropriate pump to assess the individual pump l ',()
operational readiness.
0387I II-1-23 REV. O
- li.
FNP-1-M-042 g,- sc
' PUMP RELIEF REQUEST L'
PR-12 Systems.
Service Water Pump:
P001A-A, POOlB-A, P001C-AB, POO1D-B, P001E-B Class:
3 Function:
Provide cooling water to safety-related-equipment.
Test Requirement:
IWP-4500 specifies measuring vibration at a pump housing or its structural support unless it is separated from its driver by a resilient' mounting.
Basis for Relief:
These pumps are submerged in a pit which makes'them inaccessible for' measuring vibration amplitude at the pump bearings.
Alternate Testing:
. Vibration amplitude is to be measured on each of the pump flanges horizontally.in
()
.two planes 90 degrees apart.
O 0387I II-1-24 REV. O
l;
.ENP-1-M-042 y
. PUMP RELIEF REQUEST
~
PR 13.
Systems.
Service Water Pump:
P001A-A, P001B-A, P001C-AB, P001D-B, POO1E-B Class:'
3 Function:
Provide cooling water to safety-related equipment.
Test Requirement:'
. Table IWP-4110-1 requires that-flow rate instrument accuracy be +2 percent'of full-scale.
Basis for Relief:
In order to obtain the.l.1 percent accuracy for the installed annubar flow elements,.they must be installed with at lease 3 to 4 pipa diameters downstream and 6 pipe diameters upstream.
Due to system pipe configuration, the downstream installation is in compliance O-but the upstream installation is a e
half-pipe diameter short.
The annubars are certified for a 0.1 percent repeatability.
Repeatability is a more important consideration in monitoring for pump flow degradation.
All flow measuring instrumentation associated with the annubars is in compliance with the requirements of Table IWP-4110-1.
Alternate Testing:
The installed annubar flow elements will be used to measure pump test flow rate to the requirements of Table IWP-3110-2.
l 0387I II-1-25 REV. 0
}
i.
l FNP-1-M-042
}
L PUMP RELIEF REQUEST
,3i}
l PR-14 1
System:
Service Water Pump:
P001A-A, P001B-A, P001C-AB, P001D-B, POO1E-B Class:
3 Function:
Provide cooling water to safety-related equipment.
Test Requirement:
Table IWP-4120 requires that the full-scale range of each instrument be no more than three times the reference value.
Basis for Relief:
Reference values for discharge pressure for these pumps are between 88 and 92 psig.
This would requir,e discharge pressure gauges of 0-265 psig maximum.
The accuracy required for these gauges would be 2 percent of 265 psig, which is
(~')
15.3 psig.
The installed pump discharge
(_-
pressure gauges are 0-300 16.0 psig.
Although the installed instruments are above the maximum range limits, they are essentially equal to the accuracy requirements and are therefore adequate for pump testing.
Alternate Testing:
The installed instruments will be used for taking inlet pressure measurements during pump testing.
e O
l i
0387I II-1-26 REV. O i
i l
4
o Il' FNP-1-M-042
}-4 PUMP RELIEF REQUEST-PR-15 L
ll System:
Component Cooling Water Pump:
Class:
3 Function:
-Provide cooling water to safety-related equipment.
' Test Requirement:
IWP-3100 requires that each measured test quantity be compared to the reference value of the same quantity.
Any deviations determined shall be compared to the limits given in Table IWP-3100-2.
Basis for Relief:
Section XI pump testing is performed by either varying the system resistance until either the measured differential pressure or the measured flow rate equals the corresponding reference
. ('
value, or by using a fixed resistance i
test flow path.
Varying system resistance to a repeatable reference point is not practical due to the constantly varying load demands on this normally' operating system.
The only possible fixed resistance pump test flow paths are the pump minimum flow lines.
The intent of Code required pump test data is to detect pump hydraulic degradation as indicated by small changes in the test measurements at a repeatable reference point on the pump head capacity curve.
Deviation from the reference value can be an indication of either pump degradation or a change in system resistance.
Use of the minimum flow line restricts flow rate to approximately 475 gpm and establishes the test reference point on the essentially flat portion of the head capacity curve.
At this reference point the Code acceptable range for differential pressure corresponds to a O
9 0387I II-1-27 REV. O
FNP-1-M-042 73 PUMP RELIEF REQUEST PR-15 (cont.)
Basis for Relief:
flow rate range from O gpm to (continued) approximately 2 times the reference value.
Under these test conditions pump test. flow rate deviation from the reference _value is primarily a function of change in the test flow path resistance.
Any small change in the
{
test flow path from erosion, corrosion,
~
temperature variations, etc.', will translate to a large percentage l
variation from the reference value.
]
Because of this, flow rate measurement I
would not provide any useful information j
to monitor pump operability or degradation.
Alternate Testing:
Pump differential pressure and vibration
{
measurements will be used to evaluate i
pump performance, i
n N_)
,,)
x-l 0387I II-1-28 REV. 0
1 1
FNP-1-M-042 f'N w PUMP-RELIEF REQUEST A.f
~
PR-16 System:
Diesel Generators Fuel Oil Transfer
. Pump:
P501A-A, P501B-B, P502A-A, P502B-B, P503A-A, P503B-B, P504A-A, P504B-B Class:.
3 Function:
Transfer diesel generator fuel, oil'from
.the storage tanks to the diesel generator day tanks.
Test Requirement:
Measure pump test inlet pressure, differential pressure and flow rate in accordance with the requirements of IWP-3100.and pump test duration requirements of IWP-3500.
Basis for Relief:
The diesel generator fuel' oil transfer pumps.are located inside the storage tank with the pump discharge ple'num and motor bolted to a flange on top of the
'('].
tank.
None of the pumps have installed instrumentation to measure either flow or discharge pressure.
The only
-possible flow measurement is by measuring change in day tank level over time.
Plant procedures require that day i
tank level be maintained approximately 80 percent full.
To comply with the Code requirement to run the pumps for 4
five minutes prior to taking test measurements would require draining the day tanks below a safe operating level.
. Alternate Testing:
Pump test flow rate will be obtained by measuring a change in day tank level over time.
A day tank level change of approximately 2 percent shall be timed and the flow rate determined from tank curves.
The limits of IWP-3100 shall be applied to determine alert and required action ranges.
0387I II-1-29
, REV. O l
i
.FNP-1-M-042 1
. f-PUMP RELIEF REQUEST
' d,,)/
h
.PR-17'
~;
h System:-
Diesel Generators Fuel Oil Transfer.
' Pump:
P501A-A, P501B-B, P502A-A, P502B-B,
'P503A-A, P503B-B, P504A-A, P504B-B L
Class:-
3 Function:
Transfer diesel generator fuel oil ~from the storage tanks to the diese1~
generator day tanks.
L Test Requirement:
Measure pump vibration in.accordance L
with IWP-3100.
y Basis for Relief:
The diesel generator fuel oil pumps are located inside.the storage tanks with L
the pump discharge plenum!and motor bolted-to a. flange on top of the tank.
The pumps are inaccessible for pump bearing vibration measurements.
77 -
Alternate Testing:
Motor vibration measurements will be performed quarterly in lieu'of Code required pump vibration measurements.
1
([)
0387I II-1-30 REV. O l
L
l FNP-1-M-042 l
P i
PUMP AND VALVE INSERVICE TESTING PROGRAM l
1 l
FOR FARLEY NUCLEAR PLANT j
i l
UNIT 1 SECTION III VALVE IST PROGRAM i
1 l
l O v
l l
l j
I I
I 0381I REV. O l
l
0 p
-FNP-1-M-042 I
III.
VALVE IST PROGRAM j
III.1 INTRODUCTION I
This section presents the program for. inservice testing of l
valves at Unit 1 of'the Farley' Nuclear Plant, in compliance.with-L the requirements of 10 CFR 50.55a.
This program has been, prepared to the requirements of the American Society of MechanicalfEngineers (ASME) Boiler and Pressure Vessel Code,Section XI, Subsection IWV, 1983 Edition with Addenda through Summer 1983, for ASME Class 1, 2, and 3 safety-related valves L
which are required for cold shutdown or to mitigate the consequences of an accident.
/
i III.2. VALVE IST PROGRAM CONCEPT The Valve Test Program was developed to verify the operability of systems required to perform a specific function in shutting down the reactor or mitigating the consequences of an accident.
The program specifiesSection XI or alternate testing, as appropriate,-for all~ valves which performLa function in bringing the reactor to cold shutdown or mitigating the consequences of an accident.
Valves are selected for inclusion in the test
[
program based on a review of all plent systems..
This review
. (~')
' identifies those. systems performing the Code-required v
functions.
Each Code-required system is then analyzed to determine which valves are essential for achieving cold shutdown or mitigating the consequences of an accident.
These valves are investigated to determine whether testing can be performed during normal operation.
Those valves for which quarterly testing is determined to be inappropriate are analyzed further to determine if. testing at cold shutdown is possible.
If it is determined that testing at cold shutdown is inappropriate, a i
further analysis'is performed and alternative testing procedures developed. to this section addressesSection XI testing requirements for all ASME Class 1, 2, and 3 valves which are required for cold shutdown or mitigating the consequences of an accident.
Where analysis has determined that Section XI J
quarterly testing is inappropriate, a justification for delay of test to cold shutdown is provided following the appropriate Valve Test Tables.
Relief requests describing appropriate alternative testing and justifying exclusion from Section XI testing have been prepared for valves which cannot be tested quarterly or during cold shutdown, and are provided following the appropriate Valve Test Tables.
t 0
0381I III-l REV. O l
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7 III.3 VALVE TEST LIST NOMENCLATURE 3;
' l ?..
s e.
The following abbreviations have been used f.h7the Valve Test Lists:
N n
Legend of Valve Type t
.f r/ j l
Angle valve A.
B Butterfly valve j';
CK Diaphragm valve D
s s
,. ;j J.
GA Gate valve s
3 GL Globe valve 7
s
/
SR Safety or pressure relief valve t i
f
.Stop ch9ck valve' SC
'/r Needle q
j,'
.N TW Three yay i /,
4 i
i:
[#
Legend of Valve Actui[3cr Type; [
4
/
j i
.)
e Air operated
- e j
/-
AO j
Solenoid
- '/
'5
., f ",g M
Manaal MO Motor operated
>w' Self actuating S
r s;
Legend of Valve Positions:
//
3 Normal, Fail, or Safety i.
. ?,
r.
AI As'is Closed j
L C
Open
('
O.
.N/A
- Not applicable
./ j
{
l O/C Open or closed 1
j' r
l Legend for-Fregueqcy of Test.c M
i J'
Quarterly Q
Refueling R'
Per Table IWV-3510-1 T
Y..
2 years j
Cold shutdown.
l CS Partial-stroke test exercised quarterly.
Valve PQRM disassembled during refueling and manual stroke test exercised.
'?
x1 t
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0381I
/..III-2 REV. 0 l
,4 i
]
lb 1 >
FNP-1-M-042 I h.
10(
- Valve disassembled.during refueling and manual stroke L
test exercised.
- Partial-stroke test exercised quarterly and full-stroke
' test exercised during refueling.
PQCS
-_ Partial-stroke test exercised quarterly and full-stroke test exercised during cold shutdown.
- Partial stroke test exercised during cold shutdown.
- Test deleted; see relief request.
Legend for Valve Categories Category Description A
- Valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their function.
B
- Valves for which seat leakage in the closed position is inconsequential for fulfillment of their function.
C
- Valves which are self-actuating in response to some system characteristic.
D
- Valves which are actuated by an energy source capable
\\].
/
of only one operation, such as rupture discs or explosive-actuated valves.
Note:
FNP design does not include s1ch valves.
- Valves which are both Category A and C.
Legend for Valve Testing Requirements PI
- Position indication verification, every 2 years per IWV-3300.
- Exercise test of Category A and B valves, quarterly per IWV-3411.
Safety-relief valves tested according to Table-3510-1, per IWV-3511.
Check valve exercise test, quarterly per IWV-3520, i
- Stroke time of Category A and B valves, quarterly pcr IWV-3413.
DR
- Stroke test direction:
0 - Open C - Closed FF - Forward-flow operability (check valve)
BS - Reverse-flow closure (check valve) 1 0381I III-3 REV. O
U
'FNP-1-M-042 FSV
- Fail-safe ~ verification of Category A and B valves, 0s quarterly per IWV-3415.
I
'LT
- Leakage rate test of Category A valves per IWV-3420,
- and valves. subject tx) Type C local-leak rate testing, as required by Appendix J of 10 CFR 50.
LJ - Appendix J, Type.C local leak rate test only LA
.Section XI, Category A seat leak-test only, LC - Both Appendix.J, Type C, and.Section XI, Category 16 leak test.
Legend for Headings Valve Number
- Unique valve. identification number.
. Class.ISI
--The' classification as determined for Section'XI.
Dwg..No.
- Piping and instrumentation diagram and ISI (coord.)
boundaryfdiagram on which valve location is shown.
Location on drawing where valve is shown is indicated as the coordinates (Coord.).
Valve Cat.
- Category of valve as defined in IWV-2200.
J)
Valve Size
- Nominal pipe size diameter of the valve.
Valve Type
- Type of valve (i.e.,
check, globe, gate)
Act Type
- Type of valve actuator (i.e., motor, air)
Norm.
Position
- Normal' position of valve (i.e.,
open, closed)
Fail Position
- Position to which the valve travels upon a loss-of-actuator power or air.
I Safety Position
- Position of valve when it performs its safety-related function.
l Act. or Pass.
- Valve function categorized as active (act.) or passive (pass.) as defined in IWV-2100.
Active valves are indicated with an "A".
Passive j
valves are indicated with a "P".
Relief Req.
or C.S.
Just.
- Applicable relief request numbers are indicated with an "RV" prefix.
Applicable cold shutdown justification numbers are indicated with a "CS" O
prefix.
0381I III-4 REV. O
p i
f FNP-1-M-042 i
1 rx III.4 DRAWING LIST i
~
ASME Class 1, 2,
and 3 Systems Boundary Diagram System P&ID No.
No.
Reactor Coolant (Q1B13)
D-175037/1' D-351114/1 D-175037/2 D-351114/2 RHR/LHSI(Q1E11)
D-175038/1 D-351115/1 D-175038/2 D-351115/2 D-175041 D-351118 Reactor Cavity Cooling (Q1E12)
D-175010/2 D-351108/2 Containment Spray (Q1E13)
D-175038/3 D-351115/3 Containment I. solation (Q1E14)
.D-175010/2 D-351108/2 Penetration Room Filt. (Q1E15)
D-175022 D-351126 HHSI/CVCS (Q1E21)
D-175038/1 D-351115/1 D-175038/2 D-351115/2 D-175039/1 D-351116/1 D-175039/2 D-351116/2 Reactor cavity Post-LOCA Dilution (Q1E22)
D-175019 D-351109 Post-Accident Containment Vent and Sample (Q1E23)
D-175019 D-351109
- }
Liquid Waste Disposal (Q1G21)
D-175004/2 D-351105/2
\\-
D-175042/1 D-351119/1 Steam Generator Blowdown (Q1G24)
D-175071/1 D-351122/1 Spent Fuel Fool Cooling (Q1G31)
D-175043 D-351120 Main Steam (Q1N11)
D-175033/1 D-351110/1 Auxiliary Steam (Q1N12)
D-175033/2 D-351110/2 Feedwater (Q1N21/Q1C22)
D-175073 D-351123 Auxiliary Feedwater (Q1N23)
D-175007 D-351106 Chemical Injection (N1N25)
D-175000/1 D-351102/1 Demineralized Water (Q1P11)
D-175047 D-351121 Containment Purge (Q1P13)
D-175010/1 D-351108/1 D-175010/2 D-351108/2 Sampling (Q1P15)
D-175009/1 D-351107/1 D-175009/2 D-351107/2 Service Water (Q1P16)
D-170113 D-351128 D-170119/1 D-351330/1 D-170119/2 D-351130/2 D-170119/3 D-351130/3 D-175003/1 D-351104/1 D-175003/2 D-351104/2 Component Cooling Water (Q1P17)
D-175002/1 D-351103/1 D-175002/2 D-351103/2 Service Air (Q1P18)
D-175035/1 D-351112/1 0381I III-5 REV. O
.FNP-1-M-042 J ;,* '
ASME-Class-1,12, and 3 Systems ~(cont.)
. U..-
Boundary
- Diagram System P&ID'No.
No.
Instrument Air (Q1P19)
~D-175034/1 D-351111/1-D-175034/2
' D-351111/2 D-175034/3 D-351111/3 Containment Cooling and Purge (Q1P23) 'D-175010/1-D-351108/1 L
D. G. Air' Start (Q1R43)
"D-170806/1 D-351133 D-170806/2 D-351134 D-170807/1 D-351135
'D-170807/2 D-351136 Non-Radioactive Vent (QSV47)
D-175012 D-351124 Spent Fuel Pool' Vent and Filtration
'(Q1V48)-
D-175022.,
. D-351126
' Control: Room HVAC and Filtration (QSV49)
D-175012 D-351124-D-205012.
. D-351125 D.
G. Fuel 011' Transfer-(QSY52)
D-170060 D-351132 4
. O O
0381I III-6 REV. O
\\
I-d FNP-1-M-042 nD
?
PUMP.AND VALVE. INSERVICE TESTING, PROGRAM FOR-FARLEY NUCLEAR PLANT UNIT 1=
SECTION III O
III.5 ATTACHMENT 1:
VALVE TEST LISTS AND RELIEF' REQUESTS FOR ASME CLASS 1, 2, and 3 VALVES 2
4 0
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0383I REV. O
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FNP-1-M-042
.j s COLD SHUTDOWN TEST JUSTIFICATION
( ).
i QlB13-CS-1 System:
Reactor Coolant Valve:
QVO53, QVO61 Category:
B,C Class:
1 ASME Section XI Quarterly Test Requirements:
Exercise, time, and fail.
Cold Shutdown Test Justification:
These power operated relief valves (PORVs) are controlled by the pressurizer overpressure protection system, which automatically opens two of the valves at a preset pressure.
Set pressures are established to limit undesirable opening of the spring-loaded i
safety valves.
These valves have shown
/~N
(_)
a high probability of sticking open and are not essential for overpressure protection during power operation.
The PORVs are relied upon during reactor startup and shutdown to protect the RCS from low temperature overpressurization conditions.
Therefore, testing these valves at cold shutdown will adequately demonstrate operability at the time the system's safety-related function is being performed.
Quarterly Part
{
Stroke Testing:
Valve operators are full-stroke on
}
initiation and cannot be partial-stroke i
exercised.
]
I Cold Shutdown Testing:
Exercise, time, and fail.
('\\
\\
\\-)
0360I III-1-1-3 REV. O
FNP-1-M-042 RELIEF REQUEST r
QlB13-RV-1 System:
Reactor Coolant Valve:
HV-1, HV-2, HV-3, HV-4 Category:
B Class:
2 Function:
Valves open to vent the reactor vessel.
=ASME Section XI Quarterly Test
- Requirements:
Exercise, time, and fail.
Basis for Relief:
These reactor vessel head vent valves-are. Target Rock. solenoid operated valves.
The valve position indicators are located in the solenoid coil circuit and do not provide a positive means for valve position verification or valve
[)
stroke timing.
In order to verify that the valves exercise open and reclose, it
'~'
is necessary to establish flow through the vent lines.
Since the valves vent directly to the containment atmosphere,
- a. temporary flexible vent line to an appropriate waste drain must be installed during the test to preclude spraying reactor coolant system fluid into the containment atmosphere.
Because of the flexible line used during testing, the reactor coolant system pressure must be 50 psig or less.
Testing at pressures greater than 50 psig could result in rupture of the tent line and result in an uncontrolled release of reactor coolant system fluid into the containment atmosphere.
Alternate Testing:
These valves will be full-stroke exercised and the head vent flow path verified operable at refueling or at least once every 18 months as required by the Plant Technical Specifications.
In addition, these valves will be exercised at cold shutdown if RCS
}
pressure is less than 50 psig.
0360I III-1-1-4 REV. 0
? I,
'I FNP-1-M-042 j
)
-RELIEF REQUEST QlB13-RV-2 System:
. Reactor Coolant Valve:
.QV038, QV054 Category:
AC Class:
2-Functions Containment isolation simple check valve j
(reverse flow closure for containment isolation only).
. J ASME Section XI Quarterly Test-Requirements:
Verify reverse flow closure.
Basis for Relief:*
The only method available to verify reverse flow closure is by valve leak testing during Appendix J, Type C testing at refueling.
()
Alternate Testing:-
Reverse flow closure will be verified during Appendix J, Type C testing at refueling.
1 l
e O
0360I III-1-1-5 REV. 0
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FNP-1-M-042 y'
-COLD SHUTDOWN TEST JUSTIFICATION-
" N-]).
QlE11-CS-1 System:
LHSI/RHR Valve:
QV001A, QV001B, QV016A, QV016B Category:
A Class:
1 ASME Section XI Quarterly Test Requirements:
Exercise and time.
Cold Shutdown Test Justification:
These are boundary valves between the-high-pressure reactor coolant system and the low-pressure residual heat removal system piping.
The valves are interlocked to reactor coolant system (RCS) pressure and cannot be opened with RCS pressure greater than 402.5 psig.
Defeating the interlocks to perform f) testing is not desirable, since they are pressure isolation valves.
If the inline valves were inadvertently opened during testing an inter-system-loss-of-coolant accident (LOCA) could occur.
Quarterly Part Stroke Testing:
_ Partial-valve exercising is precluded for the same reasons as full-stroke exercising.
Cold Shutdown Testing:
Exercise and time.
l 0361I III-1-2-5 REV, O l
)
I FNP-1-M-042 7s COLD SHUTDOWN TEST JUSTIFICATION n
'~
QlEll-CS-2 System:
LHSI/RHR Valve:
QV044 Category:
B Class:
2 ASME Section XI Quarterly Test Requirements:
Exercise and time.
Cold Shutdown Test Justification:
This valve is a normally closed motor-operated valve upstream of a single check valve and serves as the second high-pressure boundary valve between the RCS and the low-pressure piping of the residual heat removal (RHR) system.
Exercising during normal operation could
("~
result in an overpressurization of the RHR system piping and result in an inter system LOCA condition.
Quarterly Part Stroke Testing:
Partial-valve exercising is precluded for the same reasons as full-stroke exercising.
Cold Shutdown Testing:
Once every 3 months the downstream pressure will be measured.
If the pressure is less than or equal to 550 psig, then the valve will be full-stroke exercised.
If the pressure is greater than 550 psig, the valve will not be exercised that quarter.
If the downstream pressure prohibits quarterly testing, the valve will be full-stroke exercised at cold shutdowns.
AV 0361I III-1-2-6 REV. O
FNP-1-M-042
/
' RELIEF REQUEST Q1E11-RV-1 l
L 1
System:
LHSI/RHR I
i i
L Valve:
QV025A, QV025B L
Category:
A q
Classt.
2 Function:
Containment recirculation sump containment isolation valves.
1 ASME Section XI Quarterly Test Requirements:
IWV-3300 requirement to verify remote position indicators at least every 2 years.
Basis for Relief:
Remote position indicators will be used to verify valve position per IWV-3300.
However, visual observation of valve I
operation is not practical because it would require removal of the valve protective
'()
chamber.
Each. valve'is equipped with redundant, remote valve position indicators and displayed at three locations on the main control board.
These indications are received from four-rotor type, four train, geared limit switches which are integral components'of the Limitorque motor operators.
Diverse power supplies are utilized to energize the control board indicator lights, such that each remote position indication is an independent-unit.
Alternate Testing:
The leak rate test during each refueling outage will verify if the remote position indicators accurately reflect the closed position of the valves.
No practical means exists to verify the open position of the valves.
However, following each leak rate test, the air pressure will be relieved by opening these valves, thus verifying that the disk moves away from the seat.
In addition, visual verification of valve stem movement will be performed whenever the valve enclosure covers are removed for any other reason unless performed within the O
previous 2-year period.
This inspection will be performed at least once in a 10-year interval.
0361I III-1-2-7
, REV. O
i L
a.
j 1
FNP-1-M-042 li-RELIEF REQUEST QlEll-RV-2 i
j
-System:
LHSI/RHR H
Valve:~
QV021A, QV021B,-QVO21C, QVO42A,1QV042B Category:
AC Class:-
1.(QV021A, B, C) 2-(QV042A, B) 1 Function:
LHSI/RHR-to RCS cold leg injection line-j check valves.
'ASME Section'XI Quarterly Test Requirements:
Verify forward-flow operability.
Basis for Relief:
' Verification of forward-flow operability of these normally closed check _ valves can only be performed by injecting RHR water into the RCS.,During normal operation the low-pressure.LHSI/RHR
(). ~
operating pressure.
. Verification of pumps cannot overcome the_ higher RCS full design flow rate operability cannot-be done at cold shutdown due to back pressure from the reactor coolant system.
Verification of full-flow operability can only be done at refueling with the RCS depressurized, the reactor vessel head removed, upper internals in place, and the refueling cavity at refueling level.
Alternate Testing:
Valves wil' be forward-flow verified when the SI/LOSP test is being performed.
D 0361I III-1-2-8 REV. O
FNP-1-M-042 y7 5 RELIEF REQUEST L) '
-QlEll-RV-3 L
System:
LHSI/RHR Valve:
QV051A, QV051B,.QVO51C LCategory:
C Class:
1 Functions-HHSI/LHSI to RCS cold leg injection'line l
ASME.Section XI Quarterly. Test Requirements:
. Verify forward-flow operability.
Basis for Relief:
Verification of forward-flow operability of these normally closed check valves.
can only be performed b,y injecting high-head safety injection (HHSI) or.
low-head safety injection (LHSI) flow into the RCS..During normal operation.
/~'3 neither the HHSI or LHSI pumps can pass g
.v -
valve design flow.
In addition, testing at normal operation with injection from the HHSI. pumps would introduce relatively cold refueling water shortage tank (RWST) water into the RCS.
This would cause thermal transients to the SI nozzle and could result in thermal shock induced cracking of the nozzles.
Verification of full design flow rate 3
operability cannot be done at cold shutdown due to back pressure from the RCS.
Verification of full-flow operability can only be done at
-i refueling with the RCS depressurized, the reactor vessel head removed, upper internals in place, and the refueling cavity at refueling level, j
Alternate Testing:
Valves will be forward-flow verified during the safety injection with LOSP 3
test at refueling.
.j 0361I III-1-2-9 REV. O
ENP-1-M-042
)(-j RELIEF REQUEST
%/
Q1E11-RV-4 System:
LHSI/RHR I
Valve:
.QV021A, QV021B, QV021C
' Category:
AC Class:
1 j
. Quarterly Test j
Requirements:
Verify forward flow operability.
g I
Basis for Relief:
These 6-inch Velan swing check valves are' located in the low-head safety injection flow paths to the reactor coolant system cold legs.
Flow rate through these valves was adjusted to approximately 1350 gpm during-preoperational testing by measuring the total upstream flow rate and balancing the' flow through each line.
Individual f']
line flow rate cannot be used to verify E
individual valve operability due to lack 4
of instrumentation.
At 450 gpm each valve is opened to 100 percent of full valve lift.
1 A sensitivity evaluation has been performed to determine if failure of one valve to open can be detected by measuring the LHSI pump flow rate through the set of three paralled valves.
The evaluation determined that if one valve fails to open (stuck in the fully closed position) the total flow rate which could be expected from one pump, with the other two valves fully open, is about 3500 gpm.
Since the test acceptance criteria is a total flow rate of equal to or gret.ter than 3981 gpm, a failure of one valve to open can be detected.
In addition, the sensitivity evaluation determined that due to the available margin, the system can still meet its design criteria even if one valve only opens to 45 percent of full n
lift.
In effect, measurement of total
\\)
flow is a valid procedure to detect failure of one valve to open.
I.,
0361I III-1-2-10 REV. O
FNP-1-M-042 3-RELIEF REQUEST 1_/
1 QlEll-RV-4 I
1 i
Basis for Relief:
A review of industry documented failures (continued) has been performed to determine if the j
Velan valve design is prone to fail in l
the partially open position.
This review and discussions with the valve vendor indicated that there has been a problem with the swing' check valve j
sticking open due to the disk locking j
wire getting lodged between the disk and body.
The problem was addressed by IE l
Notice 81-03 which identified the j
problem and requested the utilities to j
evaluate the problem.
Since the notice I
was issued and the change made to the l
affected valves, there has not been any reported problem of the valves being stuck open.
Since this valve is a category AC valve, leak testing performed after valve operability i
verification would detect failure of the i
valve to fully reclose.
j
/^}
{
(-
Based on the sensitivity evaluation and j
industry history survey, a full flow j
test procedure in combination with the required valve seat leakage measurement j
provides adequate assurance that the j
valve performs properly.
]
Alternate Testing:
A full flow test will be performed on the three parallel valve set and individual valve category AC leak rate measurements will be performed at j
refueling.
If the full flow test I
criteria cannot be achieved, the system
{
will be evaluated.
If necessary, each i
valve will be investigated by installing j
instrumentation or by disassembly until I
the nonfunctioning valve is identified.
l 0361I III-1-2-ll REV. 0 l
1
FNP-1-M-042 y
RELIEF REQUEST Q1E11-RV-5
-l I
System LHSI/RHR Valve:
QV051A, QV051B, QV051C l
Category:
C Class:
1 ASME Section XI Quarterly Test Requirements:
Verify forward' flow operability.
l Basis for Relief:
These 6-inch Velan swing check valves are located in the shared low-head and high-head safety injection lines to the 4
reactor coolant system cold legs.
Flow rate through these valves was adjusted to approximately 1550 gpm during i
preoperational testing by measuring the
_ total upstream LHSI and HHSI fl~ow rates and balancing the flow through each 0
4 line.
Individual line flow rate cannot be used to verify individual valve operability due to lack of instrumentation.
At 1500 gpm each valve is open 100 percent of full valve lift.
Since these valves are shared between i
the LHSI and the HHSI systems, testing is performed with both system pumps in operation.
A sensitivity evaluation has been performed to determine ~if failure of one valve to open can be detected by measuring the LHSI pump flow rate and the HHSI pump flow rate during testing.
The impact of one of these valves i
failing to open would have the combined effect of the failure discussed by relief requests Q1E21-RV-10 and Q1E11-RV-4.
Total LHSI and HHSI flows would drop to about 3500 gpm and less than or equal to 500 gpm respectively.
Similar to the valves discussed by relief requests Q1E21-RV-10 and QlE11-RV-4, even with these valves partially opened the system can still meet the design requirements.
O 0361I III-1-2-12 REV. 0
FNP-1-M-042 RELIEF REQUEST L
h
l
. Basis for: Relief:
A review of industry documented failures.
(continued) and vendor inquiries has been performed for both the Velan and Kerotest. check
. valves.as discussed by'the' referenced-relief requests.
Based on.the sensitivity, evaluation'and I
. industry history survey, a full flow test procedure provides adequate assurance that each va'lve performs properly.
. Alternate Te' sting:
A. full flow test using both the~LHSI and.
l
- EHSI pumps will be performed at.
refueling.
If the full flow test.
' criteria for either LHSI or HHSI flow i
' rate cannot be achieved, the system will be. evaluated.. 'If necessary, each valve:
will be investigated by installing i
instrumentation or by disassembly until the nonfunctioning valve is identified.
1 i
O 0361I III-1-2-13 REV. 0
FNP-1-M-042
/~ -
RELIEF REQUEST
~' '
'QlEll-RV-6 System:
LHSI/RHR Valve:
QV032A, QV032B, QV033A, QV033B Category:
B Class:
2
' Function:
RHR HX. tube side discharge to SIS (QV032A,B) and RHR HX. bypass (QV033A,B).
ASME Section XI Quarterly Test Requirements:
Measure valve stroke time.
Basis for Relief:
Valves QVO32A,B are the RHR heat
~
exchanger outlet valves and QV033A,B are the RHR heat exchanger bypass valves.
Valves QV032A,B are normally open, fail open and valves QV033A,B are normally closed, fail closed valves.
This is the 4
required valve alignment for the LHSI mode of operation.
The RHR function of these valves is to control cooldown rate by regulating flow through the RHR heat exchangers.
Both the flow control and bypass valves modulate'to control the amount of heat. removal by the RER heat exchangers.
Valves QVO32A,B modulate in response to a manually controlled position signal and valves QV033A,B automatically modulate to adjust bypass flow in response to the set position of valves QV032A,B.
The only way to full stroke the valves is by manually adjusting the flow-control valve position control station through the full range of adjustment.
Alternate Testing:
The valves will be tested quarterly by stroking each valve through its full range of travel.
0361I III-1-2-14 REV. O
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COLD SHUTDOWN TEST JUSTIFICATION Q1E12-CS-1 System:
Reactor Cavity Cooling Valve:
QV001A,-QV001B Category:
B Class:-
-Quarterly Test Requirements:
Exercise,. time and fail.
Cold Shutdown Test Justification:
Technical Specifications impose specific limits (n1 containment temperature during normal operation.
Failure of either of these valves in the closed position could cause these limits to be exceeded at the reactor cavity sample points and would result in a forced plant shutdown.
Quarterly Part Stroke Testing:
Valves full stroke on initiation and cannot be partial-stroke exercised.
Cold Shutdown Testing:
Exercise, time and fail.
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Q
l FNP-1-M-042 f^1 R!? LIEF REQUEST U
)
System:
Containment Spray Valve:
QV002A, QV002B, QV014 Cat 6 gory:
C Class:
2 Function:
Containment spray system inside containment isolation check valves (QVOO2A,B) and RWST to containment spray pump suction line check valve (QV014).
ASME Section XI Quarterly Test Requirements:
Verify forward-flow operability.
Basis for Relief:
The only way to verify forward-flow operability during normal operation or cold shutdown would be by using the
,s pumps and injecting a large quality of
(_)
water into the containment.
Spraying the containment would result in extensive damage to safety-related equipment located inside the containment.
Alternate Testing:
The system has been modified such that spool pieces can be installed downstream of these check valves.
During refueling, these spool pieces will be installed and a full-forward-flow test performed by pumping water through these full-flow test lines to the containment refueling cavity.
Because of the time involved in installing the spool pieces and the large quantity of water necessary, this test can only be performed at refueling.
In addition, QV014 will be partial-forward-flow verified during quarterly pump testing.
AU 0363I III-1-4-3 Rev. 0
1 n.
1.
FNP-1-M-042 l
RELIEF REQUEST QlE13-RV-2 System:
Containment Spray Valve:
QV003A, QV003B Category:
A Class:
2 Function:
Containment. recirculation sump containment isolation valves.
ASME Section XI' Quarterly Test Requirements:
IWV-3300 requirement to verify remote position indicato*.c at least every 2 years.
Basis for Relief:
Remote position indicat, ors will be used to verify valve position per IWV-3300.
However,l visual. observation'of valve M
operation is not' practical, since it
(~}
would require removal of the valve h
protective chamber.
Each valve is equipped with redundant, remote valve position indicators and displayed at three locations on the main control board.
These indications are received-from four-rotor type, four train, geared limit switches which are integral components of the Limitorque motor operators.
Diverse power supplies are utilized to energize the control board indicator lights, such that each remote position indication is an independent unit.
3 0363I III-1-4-4 Rev. O
FNP-1-M-042 QlE13-RV-2 (cont.).
Alternate' Testing:
The leak 1 rate test'during each refueling outage'will verify if the remote position indicators accurately reflect-the closed position of the valves.. No practical means exists to verify the open position of the valves.
- However, following each leak rate: test, the' air pressure will be relieved by opening these. valves, thus verifying that the disk moves away from the seat.
In addition, visual verification of valve stem movement will be performed whenever the valve enclosure covers are removed for'any other reason unless performed within the previous 2-year period.
This inspection will be performed at least once in e 10-year interval.
O 0363I III-1-4-5 Rev. O
_A
i FNP-1-M-042
. (
' RELIEF REQUEST 6
Q1E13-RV-3 System:
Containment Spray Valve:
QV007A, QV007B Category:
C Class:
2 Function:
Spray additive tank to eductor line check valves.
ASME-Section XI Quarterly Test Requirements:
Verify forward-flow operability.
Basis for Relief:
The only way to verify forward-flow operability is by measuring for design flowrate through the line while operating the-containment spray pumps
- under design flow conditions.
There are no system design provisions for
( )-
performing full-flow pump testing, except whenispool pieces are installed and full-flow pump testing is performed at refueling.
Quarterly pump testing is through a small 2-inch line from the pump discharge back to the RWST.
With this test configuration,'there is no flow through'the valves, and testing for flow through the check valves is not possible without' opening additional valves which will introduce sodium hydroxide into the RWST (ECCS water supply).
Alternate Testing:
One valve will be disassembled and the disk will be manually full-stroke exercised at refueling'on a staggered test basis.
If disassembly reveals that the valve is inoperative, the other valve will be disassembled and stroked.
)
I2) 0363I III-1-4-6 Rev. O
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FNP-1-M-042 y,
COLD SHUTDOWN TEST JUSTIFICATION Q1E14-CS,
System:
Containment Isolation Valve:
QV002, QV003, QV004,-HV3657, HV3658 Category:
A Class:
2 ASME Section XI Quarterly Test Requirements:
Exercise and time (QVOO2, QV003, QV004).
Exercise, time, and fail (HV3657, HV3658).
Cold Shutdown Test Justification s -
Exercising these normally open ' valves j
closed during normal operation could i
cause a loss of sys:cm function.
A failure while exercising in a
-1 nonconservative position would cause a -
loss of the containment atmosphere
()
monitoring instrumentation.
I
. Quarterly Part Stroke Testing:
Valves full' stroke on initiation and cannot be partial-stroke exercised.
Cold Shutdown Testing:
Exercise and time (QV002, QV003, QV004).
Exercise, time, and fail (HV3657, HV3658).
l 6
O 0364I III-1-5-2 REV. O
L l:
FNP-1-M-042
~'
RELIEF REQUEST Q1E14-RV-1 l
System:
Containment Isolation Valve:
QV001 Category:
' lass:
2
.Funco
>n :
Containment isolation simple check valve (reverse-flow closure for containment isolation only).
ASME Section XI Quarterly Test Requirements:
Verify reverse-flow closure.
Basis for Relief The only method available to verify I
reverse-flow closure is by valve' leak I
testing during Appendix'J, Type C testing at refueling.
(
Alternate Testing:
Reverse-flow closure will be verified during Appendix J, Type C testing at refueling.
)
f l
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FNP-1-M-042-I I
)
i
'yt COLD SHUTDOWN TEST JUSTIFICATION
- %_5 Q1E21-CS-1 System:
SI/CVCS Valve:
QV253A, QV253B, QV253C Category:
A Class:
2 ASME Section XI Quarterly Test j
Requirements:
Exercise, time, and fail.
q Cold Shutdown Test Justification:
The number of times that t hese valves can be exercised.during normal operation is limited to as few as possible.
Each time these valves are stroked, a downstream pressure surge occurs, which-may lift the downstream relief valve QV255.
If the relief valve lifts and fails to reseat, a loss of chemical and (b-)
volume control system (CVCS) letdown
.will result in a forced plant shutdown.
Quarterly Part Stroke Testing:
Valves full stroke on initiation and cannot be partial-stroke exercised.
Cold Shutdown Testing:
Exercise, time, and fail.
v 0366I III-1-7-10 REV. O
1 FNP-1-M-042 COLD SHUTDOWN TEST-JUSTIFICATION-y LQ1E21-CS E
. System:
'SI/CVCS Valve:
.QV210,QV264-Category:
B (QV264)
C (QV210)
Class:
2 ASME Section XI Quarterly Test Requirements:
Exercise.and time (QV264).
Verify' forward flow operability (QV210).
Cold Shutdown Test i
Justification:
The only way to verify forward flow operability is by passing concentrated l
boric. acid solution through check valve j
QV210 to the charging pump suction header.
At least one boric acid ~
transfer pump is maintained in. operation O-to prevent boron from precipitating out of solution.
Exercising valve;QV264 during normal operation.would result in
. transfer of' boric' acid to the charging pump suction header., Transfer of concentrated boric acid at 230 gpm with a concentration of 7000 to 7700 ppm to the charging pump suction during normal operation would subject the plant to an unnecessary safety challenge caused by a rapid temperature decrease in the RCS and ensuing power transient
}
due to the boron addition.
Quarterly Part Stroke Testing:
Part stroke operability verification is precluded by the same reasons as full stroke operability verification.
Cold Shutdown Testing:
Exercise and time (QV264).
Verify forward flow operability (QV210).
0366I III-1-7-11 REV. 0 l
FNP-1-M-042 fg COLD. SHUTDOWN TEST JUSTIFICATION QlE21-CS-3 System:
SI/CVCS Valve:
QV254, QV257, QV258, QV565A, QV565B Category:
A (QV254, QV257, QV258)
B (QV565A, QV565B)
Class:
2 ASME Section XI Quarterly Test Requirements:
Exercise and time (QV257, QV258).
Exercise, time, and fail (QV254, QV565A, QV565B)
Cold Shutdown Test Justification:
These valves are in the.Sormal letdown and charging lines to the RCS.
Exercising during normal operation would disrupt normal RCS charging flow which could decrease significantly the
()
capability of the CVCS to provide the
\\-
proper boration ratio.
Failure of each valve in the closed position coincident with normal charging flow could result in a high RCS water level trip.
Because of these reasons and a potential for thermal shock to the Regenerative Heat Exchanger, valve testing will be delayed to cold shutdown.
Quarterly Part Stroke Testing:
Valves are equipped with full-stroke-only operators and cannot be partial-stroke exercised.
Cold Shutdown Testing:
Exercise and time (QV257, QV258).
Exercise, time, and fail (QV254, QV565A, QV565B) 0366I III-1-7-12 REV. O
FNP-1-M-042
' [^T COLD SHUTDOWN TEST JUSTIFICATION y/
Q1E21-CS-4 System:
SI/CVCS Valve:
QV336A, QV336B,1QV376A, QV376B
' Category:
B l.I Class:
2 ASME Section XI Quarterly Test Requirements:
Exercise and time.
Cold Shutdown Test i
Justification:
The refueling water storage tank (RWST) 1 line block valves are inter-locked to the volume control tank (VCT) line block valves such that both sets can not be opened at the same time.
To exercise the VCT line block valves closed would require opening the RWST line block valves.
If a RWST line block valve is
).
opened during normal' operation with a charging pump in operation RWST water would be-injected into the. reactor coolant system (RCS).
Injection of the highly borated RWST water into the RCS would adversely affect the boric acid concentration in the RCS and could cause a forced plant shutdown.
Quarterly Part Stroke Testing:
Valves full-stroke on initiation and cannot be partial-stroke exercised.
Cold Shutdown Testing:
Exercise and time.
i i
0366I III-1-7-13 REV. O L______________
1 FNP-1-M-042 L>
COLD SHUTDOWN TEST JUSTIFICATION Q1E21-CS-5 System:
SI/CVCS Valve:
QV016A, QV016B Category:
B Class:
2 ASME Section XI Quarterly Test Requirements:
Exercise and time.
Cold' Shutdown Test Exercising these valves open during Justification:
normal operation with charging pump operation is precluded by plant operating procedure.
The valves have an operating history of valve packing damage if they are exercised open during high pressure operation.
The packing
. damage results in excessive packing leakage, which can cause a forced plant 7- -
qj' shutdown for repair.
To exercise these.
valves open during normal operation I
would require realignment of the normally operating charging pump and closing of the charging pump header block valves.
If a safety injection were to occur during testing and a specific charging pump fails to start, the' ability to inject water into the reactor coolant system could be compromised.
Quarterly Part Stroke Testing:
Partial-stroke exercising is precluded by the same reasons as full-stroke exercising.
Cold Shutdown Testing:
Exercise and time.
03661-III-1-7-14 REV.,0
FNP-1-M-042 i
COLD SHUTDOWN TEST JUSTIFICATION QlE21-CS-6 System:
SI/CVCS Valve:
QV220A, QV220B Category:
C Class:
3 ASME Section XI Quarterly Test Requirements:
Verify forward flow operability.
cold shutdown Test The only way to verify full-forward-Justification:
flow operability is by pumping concentrated boric acid from the boric ac.id tank through the inline flow element (1-FT113) to the charging pump suction header.
During normal operation, at least one charging pump is in operation such that concentrated boric acid would be injected directly O
into the reactor coolant system.
The addition of concentrated boric acid to the reactor coolant system during normal operation would adversely affect plant operations and could cause a forced plant shutdown.
Quarterly Part Stroke Testing:
Partial-forward-flow operability is verified by proper operation of the boric acid transfer pumps in the normally operating pump recirculation operating mode.
Cold Shutdown Testing:
Full-forward-flow operability will be verified by measuring boric acid transfer flow rate at cold shutdown.
O 0366I III-1-7-15 REV. O
FNP-1-M-042 l 'tQ RELIEF REQUEST h
~#
QlE21-RV-1
. System:
SI/CVCS Valve:
QV026
. Category:'
'C '
Class:
2
. Function:
RWST to charging. pump suction line check valve.
ASME'Section XI l
f
]
Quarterly Test Requirements:
Verify forward flow operability.
Basis for Relief.
The-only possible full forward flow test of this valve is by operating the charging pumps and injecting full design flow into the RCS.
Dur'ing normal operations, full flow testing using the charging pumps is precluded because.the f-)g maximum pump =d1scharge pressure-is less
(_
than that required to' overcome RCS operating pressure sufficiently to inject at a flow' rate-equivalent to the RCS depressurized design flow rate.
Full or partial flow testing at cold nhutdown could only be done with a steam i;
bubble in the pressurizer.
Normal plant i
practice is'to collapso.the bubble early
)
in the shutdown procedure'and cool the l
plant down in the solid condition.
Overpressure protection during cold 4
shutdown is provided by the residual heat removal (RHR) pump suction relief valves.
Verification of valve I
operability by charging pump flow could
)
result in lifting these relief valves.
Alternate Testing:
The valve will be forwarded flow
{
verified by operating the charging pumps at refueling when filling the refueling cavity.
9 0366I III-1-7-16 REV. O
FNP-1-M-042 RELIEF REQUEST QlE21-RV-2 System:
SI/CVCS Valve:
QV032A, QV032B, QV032C, QV037A, QV037B, QV037C Category:
AC Class:
1 Function:
Accumulator discharge to RCS check valves.
ASME Section XI Quarterly Test Requirements:
Verify forward flow operability.
Basis for Relief:
The safety injection system accumulator tanks are isolated from the RCS by these normally closed check valves.
Each accumulator is charged with a nitrogen blanket from 600 to 650 psig.
This O
pressure is insufficient during operation to inject into the RCS.
If these valves were to be exercised at cold shutdown, the contents of the tank would be dumped into the RCS at the charge pressure of 600 to 650 psig which would result in the overpressurization of the RCS.
Alternate Testing:
One of these valves will be disassembled and manually full-stroke tested at refueling on a staggered test basis.
If disassembly reveals that the valve is inoperable, the remaining valves will be disassembled.
e 0
0366I III-1-7-17 REV. O
g FNP-1-M-042 1
RELIEF REQUEST
~
Q1E21-RV-3' System:
SI/CVCS Valve:
QV052, QV058,-QV115A, QV115B,'QV1150,
'QV119, QV213 Category:
AC Class:
2 Function:
Containment isolation sample check valve (reverse flow closure for containment isolation only).
-Quarterly Test Requirements:-
Verify reverse flow closure..
Basis for Relief:
The only method available to verify.
reverse flow closure is'by valve leak i
testing during Appendix.J, Type C testing-at refueling.
.p.
i d
Alternate Testing:
Reverse flow closure will be verified-during: Appendix J, Type C testing.at refueling.
0366I III-1-7-18 REV O
u
FNP-1-M-042 RELIEF REQUEST Q1E21-RV-4 System:
SI/CVCS Valve:
QV062A, QV062B, QV062C Category:
C Class:
1 Function:
Boron injection tank to RCS cold leg line check valves.
ASME Section XI Quarterly Test Requirements:
Verify forward flow operability.
Basis for Relief:
The only possible way to verify full-flow operability of these check valves is by using the CVCS charging pump flow through the boron injection tank into the RCS cold legs.
However, injecting' water into the RCS through the boron injection tank O
during power operation exposes the safety injection nozzles to thermal shock and l
interrupts normal charging and letdown.
Injection of CVCS charging pump flow at cold shutdown would result in a low temperature overpressurization of the RCS.
l Alternate Testing:
Forward flow operability will be verified at refueling as part of the integrated system safety injection with loss of offsite power (SI/LOSP) test.
O 03661 III-1-7-19 REV. 0
~
l j
4 e
J' ENP-1-M-042
(~}
RELIEF REQUEST v
QlE21-RV-5 l
1 J
System:
SI/CVCS
~
Valve:
QV063, QV068, QV072 7
Category:
B Class:
2 Function:
Safety injection (SI) to the RCS hot and cgid legs containment isolation valves.
ASME Section XI Quarterly Test Requirements:
Exercise and time.
l Basis for Relief:
Exercising these valves during normal q
operation would result in injecting j
charging water flow directly inte the RCS.
]
This diverted charging water bypasses the" l
regenerative heat exchanger which would cause thermal shocking to the.RCS piping 1
(
and would also cause an overtemperature condition in the normal CVCS letdown line.
Normal plant practice is to collapse the pressurizer steam bubble early in the.
shutdown procedure and cool the plant down in the solid condition.
This is norcally I
done well before reaching. cold shutdown.
conditions.
There is a' period of tine after reaching Technical Specification defined cold shutdown when one char ^ging
~
pump is maintained in operation.
By plant
)
procedure one charging pump is maintained
,in operation to maintain flow to the reactor coolant pump seals until thei reactor vessel"is drained down to the rmid-plane level.
If these valves were (exercised open during that period of operation, charging pump fidw would be injected directly in to the RCS.
Overpressure protection during cold shutdown operation is provided by RHR pump suction relief valves QV015A,B.
This inje.ction of charging pump flow could result in lifting these relief valves.
r-Alternate Testing:
Exercise and time during cold shutdown when
~
(_)s the RCS is drained down to the mid-plane level and all charging pumps are secured or placed in an alignment that allows testing.
03661 III-1-7-20 REV. O
FNP-1-M-042 n
RELIEF REQUEST
\\
)
QlE21-RV-6 System:
SI/CVCS 1
Valve:
QV066A, QV066B, QVO66C, QV078A, QV078B, QVO78C, QVO79A, QV079B, QV079C Category:
C Class:
1
]
Function':
Safety injection to the RCS check valves.
ASME Section XI Quarterly Test Requirements:
Verify forward flow.
Basis for Relief:
Verification of forward flow operability can only be performed by injecting charging water into the,RCS.
The charging pumps have insufficient head to overcome normal RCS operating pressure for a full flow test.
Partial testing 6')
using the charging pumps would inject
's >
CVCS water which has bypassed the regenerative heat exchanger and would result in thermal shock to the RCS j
piping.
Verification of full design flow rate operability cannot be done at d
cold shutdown due to back pressure from f
the RCS.
Verification of full flow 4
operability can only be done at refueling with the RCS depressurized, j
the reactor vessel head removed, upper i
internals in place, and the refueling W
cavity at refueling level.
I Alternate Testing:
Forward flow operability will be verified at refueling as part of the integrated system SI/LOSP test.
p 0366I III-1-7-21 REV. O
m rc' f.-
ENP-1-M-042 N
a
'RELIEFJREQUEST
- f')y QlE21-RV-7 er System
- .
SI/CVCS*'"
Valve:
QV122A, QV122B, QV122C Category:
C:
<v class:
2 Function:
Charging pump discharge line~ check valves.
ASME SECTION XI Quarterly. Test Requirements:
Verify forward flow operability.
Basis'for Relief.:
These charging pump discharge check valves cannot be verified for full flow operabi_ity quarterly.
Normal operating' charging flow is automatically controlled by downstream flow control valve QV347 in response to RCS operating conditions.
To inject full flow into the RCS during normal operation would result"in undesirable RCS boron concentrations and system pressure, temperature and level transients.-
Full-stroke exercising'these valves at cold shutdown would result in RCS pressure and level transients due to-limitations on letdown capability.
Alternate Testing:
Valves will be partial-stroke exercised qaarterly and verification of full forward flow operability performed at refueling.
O 0366I III-1-7-22 REV. O
..r
{. q( - \\
5 n
E' 7
FNP-1-M-042 gt m
RELIEF REQUEST.
-QlE21-RV-8
-System:
SI/CVCS Valve:
QV249A, QV249B a.
Category' A
4 iClass:
2 Function:
CVCS seal water flow'to the reactor
.. f coolant pumps containment isolation fc valves.
'ASME Section XI Quarterly Test Requirements:
Exercise and time.
Basis for Relief:
Exercising these valves during normal operation or at cold shutdown results in a loss of normal seal water to the RCS pump seals.
If. seal water.is terminated, reactor coolant is forced
./~T from the high pressure RCS into the
~\\/
seals.
Reactor coolant normally contains.a high particulate matter-concentration which11s carried with RCS inleakage and contaminates the seals.
Westinghouse has studied this problem (see Westinghouse Document NSD TB-7515, 1978)'and recommends that seal flow be maintained at cold shutdown as well as during normal operations.
Alternate Testing:
Exercise and time at cold' shutdown when the RCS is vented or open to the atmosphere.
O 0366I III-1-7-23 REV. O
..h
(
1 FNP-1-M-042.
RELIEF REQUEST-
_s Q1E21-RV-9 System:
SI/CVCS Valve:
QV326A, QV326B, QV327A, QV327B Category:
B Class:
2 Function:
CVCS charging pump discharge header block valves.
ASME'Section XI Quarterly Test Requirements:
Exercise and time.
Basis for Relief:
During normal operation only one charging pump.is.in operation which supplies both charging water to the RCS and seal water to-the RCS pump seals.
,Due to system design configuration, exercising any of these valves will ft terminate either normal charging flow cr
\\m) seal water flow.
Disruption of charging water flow would decrease significantly the capability of the CVCS to provide the proper boron concentration.
If seal water is terminated, reactor coolant is I
forced from the high pressure RCS into the seals and can cause seal degradation.
Valves full-stroke on initiation and cannot be partial stroke exercised.
Alternate Testing:
Exercise and time at cold shutdown when the RCS is vented or open to atmosphere.
\\
l l
l 0366I III-1-7-24 REV. O l
$1_____-.
p FNP-1-M-042 L
}
RELIEF REQUEST Q1E21-RV-10' System:
SI/CVCS
- Valve:
-QV062A, QV062B, QV062C, QVO66A, QV066B, QV0660, QV078A, QV078B, QV078C, QV079A, QV079B, QV079C Category:
C Class:
1
~
Function:
Safety injection to the RCS check valve.
ASME Section XI Quarterly Test Requirements:
Verify forward flow operability.
Basis for Relief:
These Kerotest check valves are located in the parallel high head injection flow paths to the reactor coolant. system.
Flow rate through each valve was adjusted to approximately 200 gpm during preoperational testing by measuring the s'
total upstream flow rate and balancing the flow through each line.
Individual line flow rate cannot be used to verify individual valve operability due to lack of instrumentation.
At 200 gpm each 1
valve in opened to about.70 percent of full valve lift.
A sensitivity evaluation has been performed to determine if failure of one valve to open can be detected by measuring.the high-head safety injection / safety injection (HHSI/SI) pump flow rate through each three valve set.
The evaluation determined that if one valve fails to open (stuck in the fully closed position) the total flow rate which could be expected from one pump, with the other two valves fully open, is less than or equal to 500 gpm.
Since the test acceptance criteria is a total flow rate of equal to or greater than 600 gpm, a failure of one valve to open can be detected.
In addition, the sensitivity evaluation determined that 0366I III-1-7-25 REV. 0
a FNP-1-M-042 Us)(;
L/'
RELIEF REQUEST.
.Q1E21-RV-10 Basis'for' Reliefs due tolavailable margin the~ system.can I
(continued).
still-meet its designLeriteria even,1f I
one valve only opens to.35 percent'of i
full' lift.
In effect, measurement ~of-
~
O total flow is a' valid. procedure to.
detect failure of one valveLto open~from the fully closed.to 35-' percent of' valve lift. position.
A review.of industry' documented failures q
has been-performed to-determine-if-the Kerotest valve design is prone.to
' failure.in the 35 percent to 70. percent of valve. lift. range where measurementiof total flow will not detect. valve failure.
Only one failure for 1/2-inch to 2-inch Kerotest' check valves was:
found.
This failure occured in a carbon steel valve where rust and corrosion buildup prevented the disk from opening.
No failure for the' stainless E(')
steel Kerotest 9000 series model. valves installed at ENP-1-was found.
The valve vendor was also contacted'to verify the industry survey.
The'results of both' the industry survey-and vendor. inquiry verify'that these particular valves have not.had any history of the. internals sticking in either the: fully. closed or partially open position during operation.
Based on the sensitivity evaluation and industry history survey, a full flow-test procedure provides adequate assurance that each valve performs properly.
Alternate Testing:
A full flow test will be performed on each three-valve set at refueling.
If the full' flow test criteria cannot be achieved, the system will be evaluated.
If necessary, each valve will be investigated by installing
.H instrumentation or by disassembly until the nonfunctioning valve is identified.
LO 0366I III-1-7-26 REV. O
r FNP-1-M-042 l
fy, RELIEF REQUEST' QlE21-RV-11 System:
SI/CVCS Valve:
QV077A, QV077B, QV077C Category:
AC Class -
1 Function:
HHSI to RCS hot leg injection line check valves.
ASME Section XI Quarterly Test Requirements:
Verify forward flow operability.
Basis for Relief:
Verification of forward flow operability of these normally closed check valves can only be performed by injecting full design HHSI flow into the RCS.
During normal operation the maximum pump discharge pressure is less than that required to overcome RCS operating
\\-
pressure sufficiently to inject at a flow rate equivalent to the RCS depressurized design flow rate.
In addition, testing at normal operation with injecting from the HHSI pumps would cause thermal transients to the SI nozzle and could result in thermal shock induced cracking of the nozzles.
Verification of full design flow rate operability cannot be done at cold shutdown due to back pressure from the RCS.
Verification of full flow operability can only be done at refueling with the RCS depressurized, the reactor vessel head removed, upper internals in place and the refueling cavity at refueling level.
Alternate Testing:
Forward flow operability will be verified at refueling as part of the integrated system SI/LOSP test.
1 1
0366I III-1-7-27 REV. O
FNP-1-M-042
<~g RELIEF REQUEST
~
System:
SI/CVCS Valve:
QV115A, QV115B, QV115C Category:
AC Class:
2 Function:
CVCS seal injection to RCS pumps.
Quarterly Test 1
Requirements:
Verify forward flow operability, i
Basis for Relief:
These valves must remain open to allow operation of the reactor coolant pumps and these pumps are required to be f
operable by Technical Specifications j
prior to entry into mode 3.
Technical 1
Specification 3.4.7.2.e requires a total flow of no more than 31 gpm through all
(~'
three valves.
Administrative controls
\\-
require a flow of at least 6.7 gpm through each valve.
i Alternate Testing:
The total flow of less than 31 gpm will be monitored every 31 days per Technical Specifications.
If flow drops below 1
6.7 gpm a plant main control board alarm is actuated and flow is reestablished via annunciator response procedures.
i 1
0366I III-1-7-28 REV. 0
FNP-1-M-042
(~N RELIEF REQUEST w/
QlE21-RV-13 System:
SI/CVCS Valve:
QV121A, QV121B, QV121C Category:
C Class:
2 Function:
Charging pump min. flow line check valves.
- e. ASME Section XI Quarterly Test Requirements:
Verify forward flow operability.
Basis for Relief:
In verifying full forward flow operability would require measuring the flow rate through each of the charging pump minimum flow lines.
Neither the individual minimum flow lines'nor the common header is instrumented to measure
,_s
(
)
flow rate.
u/
Alternate Testing:
One of these valves will be disassembled and inspected at refueling on a staggered basis.
If disassembly reveals that the valve is inoperable, the remaining valves will be disassembled.
0366I III-1-7-29 REV.,O
cr.
l FNP-1-M-042 r")
RELIEF REQUEST
'N J
'Q1E21-RV-14 l:
System:
SI/CVCS Valve:
QV077C Category:
AC Class:
1 Function:
HHSI to RCS hot leg injection line check-valve.
ASME S ution XI Quarterly Test Requirements:
Verify forward flow operability.
Basis for Relief:
This 6-inch Velan swing check valve is located in the high head injection flow path downstream of Kerotest check valve QV079C.
Flow rate through this valve was adjusted to approximately 200 gpm during preoperational testing by O
measuring the total upstream flow rate and balancing the flows through valves QV079A,B,C.
Individual line flow rate cannot be used to verify valve operability due'to lack of instrumentation.
The sensitivity evaluation discussed by relief request Q1E21-RV-10 for valves QV079A,B,C also addressed failure of this valve to open.
The evaluation concluded that total flow rate is a valid procedure to detect failure of either QVO77C or QV079C to open.
A review of industry documented failures has been performed to determine if the Velan valve design is prone to fail in the partially open position.
This review and discussions with the valve vendor indicated that there has been a problem with the swing check valve sticking open due to the disk locking wire getting lodged between the disk and body.
The problem was addressed by IE
(~/)
Notice 81-03 which identified the
\\_
problem and requested the utilities to 0366I III-1-7-30 REV. O
FNP-1-M-042
,^
RELIEF REQUEST
-(
Q1E21-RV-14 Basis for Relief:
evaluate the problem.
Since the notice l
(continued) was issued and the change made to the i
affected valves, there has not been any reported problem of the valves being stuck open.
Since this valve is a l
category AC valve, leak testing I
performed after valve operability
)
verification would detect failure of the I
valve to fully reclose.
Based on the sensitivity evaluation and I
industry history survey, a full flow test procedure in combination with the required valve seat leakage measurement l
provides adequate assurance that the valve performs properly.
Alternate Testing:
The full flow test proc,edure used to verify operability of valves QVO79A,B,C
{
and the category AC leak rate j
measurement will be performed at
,,s
(
)
refueling.
If the full flow test
'~'
criteria cannot be achieved, the system will be evaluated.
If necessary, each valve will be investigated by installing 1
instrumentation or by disassembly until
)
the nonfunctioning valve is identified, i
l I
'l 1
1 l
I
/
4 l
1 0366I III-1-7-31 REV. O l
l l
FNP-1-M-042
-j3 RELIEF REQUEST i
QlE21-RV-15 System:
SI/CVCS Valve:
QV077A, QV077B Category:
AC Class:
1 Function:
HHSI to RCS hot leg injection line check valves.
ASME Section XI Quarterly Test Requirements:
Verify forward flow operability.
Basis of Relief:
These 6-inch Velan swing check valves are located in the LHSI hot leg injection flow paths downstream of where the HHSI injection lines tie into the LHSI lines.
These flow paths are only aligned during hot leg recirculation
/'S flow to the reactor coolant system.
The
(-)
emergency core cooling system design basis requirement during the hot leg recirculation phase is that sufficient flow be provided to the core to maintain inventory, due to boil-off.
The present analysis demonstrates that with one train operating, and one line spilling, sufficient flow is injected from the HHSI pumps to satisfy flow requirements.
As such, there is no requirement for LHSI flow through valves QV076A,B or QVO77A,B.
Valves QV077A,B are downstream of HHSI injection valves QVO79A,B.
This is the same valve configuration as valves QVO77C and QV079C as discussed by relief requests QlE21-RV-10 and QlE21-RV-14.
Alternate Testing:
The full flow test procedure used to i
verify operability of valves QVO79A,B,C and the category AC leak rate measurements will be performed at refueling.
If the full flow test criteria cannot be achieved, the system will be evaluated.
If necessary, each valve will be investigated by installing instrumentation or by disassembly until the nonfunctioning valve is identified.
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n FNP-1-M-042:
- (-
RELIEF' REQUEST 9-r Q1G21-RV-1 System
. Liquid Waste Disposal Valve:-
QV204, QV291 Categoryt
.AC Class:
2 Function:-
Containment isolation' simple check valve (reverse flow' closure for containment isolation only).
ASME Section'XI Quarterly Test Requirements:
Verify reverse flow clocure, s
.1 Basis'.for Relief:
The only method available to verify reverse flow closure is by valve leak' testing during Appendix J, Type C, testing at refueling.
')O -.
Alternate Testing:
Reverse flow closure will be verified.
during Appendix J, Type C, testing at refueling.
i O
0373I III-1-10-3 REV. O
,(
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Q D _ SdV SdV SdV SdV SdV SdV Sdv SdV SdV toa toa toa toa toa toa toa toa toa r
fO ie.Sts l q.u eeCJ RR IL -
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t-FNP-1-M-042.
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COLD SHUTDOWN TEST JUSTIFICATION I
w i.
Q1N11-CS-1 System:
Main Steam Valve:
QV001A, QV001B, QV001C, QV002A, QV002B, QV002C Category:
BC Class:-
2 ASME Section XI Quarterly Test Requirements:
Exercise, time, and fail.
Cold Shutdown Test Justification:
Exercising.these' valves during normal operation isolates one line of steam flow to the turbine and would cause a severe pressure transient in the main steam line which could result in a forced plant shutdown.
Reducing power-level to perform testing without causing
-(_g a transient would significantly impact j
plant operations and power production.
Quarterly Part Stroke Testing:
Valves are equipped with a partial-stroke closed exerciser and will be partial-stroke exercised quarterly.
Cold Shutdown Testing:
Exercise, time, and fail, l
4 4
4 0367I III-1-13-4 REV. O i
FNP-1-M-042
\\.)/
COLD SHUTDOWN TEST JUSTIFICATION
/
Q1N11-CS-2 System:
Main Steam Valve:
QV003A, QV003B, QVCO3C, QV003D, QV003E,.
QV003F Category:
B Class:
2 ASME Section XI Quarterly Test Requirements:
Exercise, time, and fail.
Cold Shutdown Test i
Justification:
These valves are interlocked with the i
main steam isolation valves and cannot be opened when the main steam isolation valves are open.
Quarterly Part
,s' Stroke Testing:
Valves are full stroke on initiation and
()
cannot be partial-stroke exercised.
Cold Shutdown Testing:
Exercise, time, and fail.
i l
P.
V 0367I III-1-13-5 REV. O
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' ENP-1-M-042 i
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j f COLD SHUTDOWN TEST JUSTIFICATION Q1N21-CS-l' System:
. Valves
.QV001A, QVOO1B,. QV001C Category:
BC Class:
'2 ASME'Section XI l
Quarterly Test, Requirements:
Exercise and time.-
Cold Shutdown Test Justification:
Exercising.these valves closed during normal operation would result in a' loss of feedwater to the associated steam generator.
' Isolation of feedwater flow during normal operation'wouldicause a severe steam generator operating transient which could result in a forced
- O-plant shutdown and/or reactor trip.
Quarterly Part Stroke Testing:
Valves full stroke on initiation and cannot be partial-stroke exercised.
Cold Shutdown Testings.
EyArcise and time.
O 0369I III-1-15-2 REV. O
FNP-1-M-042:
COLD SHUTDOWN. TEST JUSTIFICATION Q1C22-CS-1L System:
Feedwater-Valve:
.FCV478, FCV479, FCV488, FCV489, FCV498,.
FCV499 Category:
B Class:
Quarterly Test Requirements:
Exercise,' time, fail.
Cold Shutdown Test w
Justification:
Exercising feedwater flow control valves FCV478, FOV488, and FCV498 closed during normal operation would result in a loss of flow to the associa.ted steam generator.
Isolation'of feedwater flow would cause a severe steam generator operating transient which could result.
.(
).
in a. forced plant-shutdown and/or a reactor trip.- Exercising.the feedwater
'M flow control bypass valves'FCV479, FCV489, and'ECV499 causes a severe system operating transient which could result in a forced plant shutdown and/or l
Quarterly Part Stroke Testing:
Valves full stroke on initiation and
)
cannot be partial-stroke exercised.
Cold Shutdown Testing:
Exercise, time, and fail.
l o,
0369I III-1-15-3 REV. O r
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FNP-1-M-042
-COLD SHUTDOWN TEST. JUSTIFICATION-Q1N23-CS-1 Systems'
. Valve:
QV002-(A throught H),: QV003, QV006, QV007A, QV007B,-QV011A,'QV011B, QV011C1
- Category
C l'
Class:
'3 ASME'Section XI L,
Quarterly Test' Requirements:
Verify forward-flow operability Cold' Shutdown Test.
Justification:
The only way to verify forward-flow operability.of these valves is by l
operating the auxiliary feedwater pumps and injecting'relatively cold condensate-water directly into the-steam.
generators.
The: introduction'of cold water into the hot steam generators f'lk during operation would result in large thermal shock to the feedwater nozzles and'could cause cracking of the nozzles.
Quarterly Part Stroke Testing:
Valves will be partial-forward-flow verified during pump testing.
Cold Shutdown Testing:
Full-forward-flow operability will be
. j verified by injecting into the steam
)
generators at cold shutdown.
l 1
l l
a e
9 i
e 0371I III-1-16-6 REV. O
Il ENP-1-M-042-RELIEF REQOEST
.dr-Q1N23-RV-1 System:
Auxiliary Feedwater Valve:
QV006, QV007A, QV007B Category:
C Class:
3 Function:
Condensate storage tank to auxiliary feedwater pump suction line check valves.
ASME Section XI Quarterly Test Requirements:
Verify reverse flow closure.
Basis for Relief:
There are no system design provisions for verification of reverse flow closure.
The only'possible test method would involve isolating the condensate
_ storage tank, draining a large'section of piping, and injecting service water t',')
into the auxiliary feedwater system.
A/
The service water is of poor quality and would contaminate the auxiliary feedwater piping.
It cannot be guaranteed that flushing will remove all contamination after testing.
Any contaminants which remain in the piping may be injected into the steam generators which could adversely affect secondary water chemistry and contribute I
to steam generator degradation.
Alternate Testing:
One of the QV007A, B valves will be disassembled, exercised, and visually inspected at refueling and the alternate valve will be disassembled during the next refueling.
Only one valve will be inspected at each refueling unless it fails to pass inspection.
Failure to pass inspection will initiate disassembly and inspection of the other valve.
Valve QV006 will be dis-assembled, exercised,and visually L
inspected during each refueling.
O 0371I III-1-16-7 EEV. O
l l
FNP-1-M-042
~N RELIEE REQUEST L 'J l
Q1N23-RV-2 System:
Auxiliary Feedwater Valve:
QV013A, QVOl3B, QV014A, QV014B, QV014C Category:
B Class:
3 Function:
Service water backup supply to auxiliary feedwater pump suction.
ASME Section XI Quarterly Test Requirements:
Exercise and time.
Basis for Relief:
Exercising these valves open during normal operation or cold shutdown would introduce chlorides and fluorides into the auxiliary feedwater system and subsequently into the steam generators.
The presence of chlorides and fluorides
(~)
in the secondary water chemistry have
\\-
been proven to contribute to steam generator degradation.
Initiation of the auxiliary feedwater during testing would inject a large quantity of service water directly into the steam generators.
The only way to isolate the service water system from the auxiliary feedwater system to perform testing is by closing in line manual block valves QV015E, QV016A, and QV016B.
If an auxiliary feedwater initiation occurred during testing, one train of auxiliary feedwater would be disabled.
In addition, there is no way to verify that subsequent flushing of the affected lines has removed all of the service water contaminants.
Alternate Testing:
Valves will be exercised and timed at refueling when the service water system can be isolated from the auxiliary feedwater system and extensive flushing of any residual service water can be performed.
ry b
0371I III-1-16-8 REV. O
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(
'FNP-1-M-042 RELIEF REQUEST
'k/'
l:'
QIP11-RV-11 i
r.
l6 i.
i l,-
. Demineralized Water System:.
i Valve:-
' QVOO2 Category:
'AC'
Class:
2 Function:
Containment isol'ationLsimple check" valve.
.;(reverse-flow closure for containment l.
- isolation only).
ASME Section XI Quarte rly.-Te st '
y Requirements:
Verify reverse-flow closure..
1 Basis for Relief:
The:only method-available'to verify.
1 L
reverse,. flow closure is by valve leak testing during Appendix J, Type C,:
testing at.l refueling.
Alternate Testing:
Reverse flowEclosure will-.be verified
-l during Appendix J,-Type C, testing'at refueling.
i I
i l.
0376I III-1-18-2 REV. O 2
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ly.
s.
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em
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Jr FNP-1-M-042-l
- f"N COLD' SHUTDOWN TEST JUSTIFICATION
%).
Q1P13-CS-1 Systems-
- Containment Purge L
Valve:
QV281, QV282, QV283, QV284 Category:
A Class:
2 ASME Section XI Quarterly Test Requirements:.
Exercise, time, and fail.
' Cold Shutdown Test Justification:
If these valves are open during a LOCA, the~ valve operators are incapable of closing the valves against accident. flow l
conditions.. Plant Technical Specifications require' maintaining these
- valves closed during plant operating modes 1, 2,
3, and 4.
l )
Quarterly Part
! Stroke Testing:
Valves are administratively maintained closed during normal. operation.
Cold Shutdown Testing:
Exercise, time, and fail.
4 0378I III-1-19-3 REV. 0
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7-r f
FNP-1-M-042' R
-,s COLD' SHUTDOWN' TEST JUSTIFICATION
' (,.
QlP16-CS-1 j
l System:
Service. Water
.j 1
Valve:
QV514, QV515, QV516, QV517
. Category:
.B Class:
3 I
Quarterly Test i
Requirements:
Exercise and time.
Cold Shutdown Test Justification:
Exercising these valves during normal operation isolates service water from l
normally operating equipment in the turbine building.
The system is designed to automatically. isolate service water to the turbine building on i
a high flow condition.
Exercising these valves during normal. operation couldt
.O.-
automatically isolate all~ service water result in a high flow signal which would flow and cause a turbine trip.
Quarterly Part Stroke Testing:
Valves full stroke on initiation and j
cannot be partial-stroke exercised.
Cold Shutdown I
Testing:
. Exercise and time.
i i
i l
I ])
i i
0382I III-1-21-7 REV. O
m l
'i FNP-1-M-042 l
-s(
COLD SHUTDOWN TEST JUSTIFICATION l
f Aq_/4 1
QlP16-CS-2 j
I
)
u u-
_ System:
Valve:
QV043A,: QV043B, QV043C,'QV043D
' Category _
B.
a
)
1
. Class:
-l Quarterly Test j
Requirements:
Service water emergency. return from the-l containment air coolers.
1 Cold Shutdown Test 1
C Justification:-
Cycling of these valves can cause a
]
. pressure surge in the service water i
system'which results in service water D
automatically' isolating to the turbine 3
building.
Quarterly Part l
(
StrokeLTesting:
Valves full-stroke closed on! initiation 1
and cannot be part-stroke exercised.
]
l Cold Shutdown Testing:
These valves will'be full-stroke tested a
for operability at each cold shutdown.
[
I L
i I
4 l
O-V 0382I III-1-21-8 REV. 0
FNP-1-M-042 rN RELIEF REQUEST q.,f QlP16-RV-1 System:
Service Water Valve:
QV071, QV072, QV081 Category:
A Class:
2 Function:
Service water to reactor coolant pump pump motor cooler containment isolation valves.
ASME Section XI Quarterly Test Requirements:
Exercise and time.
Basis for Relief:
These are the containment isolation valves in the RCS pump motor cooler lines.
A loss of cooling water for more than a few minutes could result in extensive damage to the reactor coolant
[)
pump motors.
Plant operating procedures require operation of at least one RCS pump at RCS temperatures above 160* F for hydrogen control of RCS water.
For short duration cold shutdowns where the RCS temperature is maintained near 200*
F, it is felt that stopping cooling water to the operating pump motor could contribute to motor degradation and result in unnecessary repairs.
Valves full stroke on initiation and cannot be partial-stroke exercised.
Alternate Testing:
Exercise and time at cold shutdown when all reactor coolant pumps are secured.
0382I III-1-21-9 REV. O
7i
,nn-
.a,
p<
FNP-1-M-042 o'
. RELIEF. REQUEST:
i Q1P16-RV-2 1
~ System:
' Valver.
- QV075 n-
^
~
-i Category:
l AC -
.a
' ' Class:
2-i i
.3
' Function:
ContainmentLisolation simple che~k valve.
c (Reverse-flow closure for.c,ontainment isolation only)..
ASME Section XI-Quarterly Test.
Requirements:
iVerify: reverse-flow closure.
T 4 Basis'for' Relief:
The.only. method available to verify.
reverse flow closure is by valve leak testing during Appendix.J, Type C,.
. testing at. refueling.
Alternate. Testing:
, during. Appendix J,. Type C, testing at Reverse-flow closure will be verified
]
).
refueling.
A O
l 4
0382I III-1-21-10 REV. O
FNP-1-M-042 e
?
,c RELIEF REQUEST
\\
)
' ~ '
Q1P16-RV System:
Valve:
QV564, QV565 Category:
C Class:
3 Function:
Service water return from diesel generator header line check valves.
ASME Section XI Quarterly Test Requirements:
Verify' forward flow operability.
Basis for Relief:
There are no system design provisions for verification of full. forward flow operability.
Alternate Testing:
Partial-stroke operability will be verified in conjunction with diesel
(~T generator testing by monitoring D.G.
Al jacket cooling water temperature.
In addition, one valve will be disassembled and visually inspected at each refueling.
Failure to pass inspection will initiate disassembly and inspection of the other valve.
0382I III-1-21-11 REV. O
l a
FNP-1-M-042 f^j.
RELIEF REQUEST v
QlP16-RV-4 System:
Service. Water Valve:
QV635A, QV635B, QV636A,. QV636B Category:
C Class:
3 Function:
Nontreated service water to the service water pump seals'and motor coolers.
(QV635A, _B) and treated service water to the SW pump seals and motor coolers (QV636A, B).
ASME Section XI Quarterly Test Requirements:
Verify forward flow operability (QV635A,B,).
Verify reyerse-flow closure-(QV636A,B).
Basis for Relief:
There'are no system design provisions (f
for verification of either full forward.
flow operability or reverse-flow closure.
Alternate Testing:
Partial-stroke operability is verified during normal operations by monitoring pump motor temperature.
In addition, one valve from QV635A, B and one valve from QV636A, B will be disassembled, exercised, and visually inspected at each refueling.
The alternate valve from each group will be disassembled, exercised, and visually inspected at the next refueling.
Only one valve from each group will be disassembled at each l
refueling unless it fails to pass inspection.
Failure to pass inspection K
l will initiate disassembly of the other
/
valve from its associated group.
l 0382I III-1-21-12 REV. O
e FNP-1-M-042'
'N.hL v'
RELIEF; REQUEST
)
QlP16-RV-5 System:
Service Water Ve.1ve:
QV552, QV553, QV554, QV555, QV556 Category:
C Class:
3 Functions.
Service water pump discharge check valves.
ASME Section XI Quarterly Test Requirements:
Verify reverse flow closure.
Basis for Relief:
The number of service water pumps in operation varies from a minimum _of two to all five pumps, depending on operational and environmental conditions.
During periods when more than two pumps are required, it is not
.I'.
possible to perform individual valve reverse-flow-closure verification without terminating cooling water flow to essential operating equipment, which could result in equipment damage or a forced plant shutdown.
Alternate Testing:
Reverse-flow closure will be verified only for those service water pumps:which are idle.
Verification will be performed during pump switching and pump shutdown unless reverse flow closure has been verified within 90 days.
f 0382I III-1-21-13 REV. 0
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R
u FNP-1-M-042 RELIEF REQUEST Q1P17-RV-1 System:
Component Cooling Water-Valve:
QV082, QV097, QV099, HV3045, HV3184 CatOgory:
A Class:
2 Function:
Component cooling water to the reactor coolant pump thermal barriers and bearing oil coolers.
ASME Section'XI Quarterly Test Requirements:
Exercise and time (QV082, QV097, QV099).
Exercise, time, and fail (HV3045, HV3184).
Basis for Relief:
These are the containment isclation valves in the RCS pump thermal barrier and bearing oil cooler lines.
A loss of cooling water i
for more than a few minutes could result in
{
-,O '
extensive damage to the reactor coolant pumps.
Westinghouse Document 1B5710-100-07A recommends that cooling water be provided to
]
the pumps at all times when RCS temperature l
is above 200 F.
In addition, plant operating procedures require operation of at j
least one pump at RCS temperatures above i
160* F.
for hydrcgen control of the RCS water.
For short duration cold shutdowns
(
where the RCS temperature is maintained near l
200*
F.,
stopping cooling wat er to the operating pump could contribute to pump degradation and result in unnecessary pump repairs.
Valves full stroke on initiation and cannot be partial-stroke exercised.
Alternate Testing:
Exercise, time, and fail (as appropriate) at cold shutdown, when all reactor coolant pumps are secured.
1 l
0385I III-1-22-5 REV. O l
l 1
FNP-1-M-042-l L
i RELIEF-REQUEST-1
~~
QlPl7-RV-2.
System:
Component Cooling Water-
-Valve:
QV083,-QV159 Category:
AC Class:
2
. Function:
Containment isolation simple check valve (reverse-flow closure for containment isolation only).
'ASME Section XI Quarterly Test
. Requirements:
Verify reverse flow closure.
l l
Basis for. Relief:
The only method available to verify reverse-flow closure is by valve leak testing during Appendix J, Type C, testing at refueling.
1
.O Alternate Testing:
Reverse-flow closure will be verified i
during Appendix J, Type C, testing at refueling.
O 0385I III-1-22-6 REV. O
[
t FNP-1-M-042 i
. RELIEF REQUEST QlP17-RV-3 System:
Component Cooling Water Valve:
QVO87A,-QVO87B, QVO87C J
Category:
C Class:
3
~i Function:
These check valves will close.to protect the low pressure component cooling water i
l (CCW) piping.from RCP thermal barrier.
J L
leakage.
ASME Section XI Quarterly Tes:
)
Requirements:
Verify reverse-flow closure.
{
Basis for Relief:
There are no installed taps or position f
indicators'that could be used to verify
, reverse flow closure.
To verify reverse flow closure, a spool piece in each line i
/~T between the valve and the reactor kl coolant' pump must be removed and an external fluid source connected to the i
line flange.
The only time these spool i
pieces aro' removed is during pump maintenance / repair during refueling outages.
To remove the spool pieces for the sole purpose of' valve testing would require draining and waste processing a large amount of chromated water.
This type of test procedure involves an excessive amount of time and personnel exposure to hazardous chemicals and j
could cause delays in plant-startup.
Alternate Testing:
Valve testf.ng will be performed only j
when the spool pieces are removed to perform pump maintenance / repair at refueling. If there is no pump maintenance / repair performed during a refueling outage, valve testing will be delayed until pump maintenance / repair is performed.
Failure during testing will
)
initiate testing of the other two valves.
l l
I i
0385I III-1-22-7 REV. O l
q o
V p
$?
'ENP-1-M-042
(~
p.-
L p,A"-(
! RELIEF REQUEST l_ V' p
T QlPl7-RV-4 I*
L,
' System:
Component Cooling ~ Water Valve:'
'HV3067, HV3095, HV3443
-Category:
-A Class:
2 Function:
CCW to,the RCS excess letdown and drain tank heat. exchanger containment.
isolation valves.
ASME Section'XI
-Quarterly Test Requirements:
Exercise, time, and fail.
9 Basis for Relief:
Exercising these valves closed creates a pressure / flow transient'in the RCS pump thermal barrier and cil cooler lines.
Pressure and. flow are monitored at the discharge of-the thermal barrier cooling f
water lines and will automatically close
- t valve HV3184 on an increase of pressure or flow rate.
Operating history indicates that the transient caused by closing these valves is sufficient to cause HV3184 to close.
Loss of cooling water to the pumps for more than a few minutes could result in extensive damage to the pumps.
Plant operating procedures require maintaining cooling water flow to the RCS pumps at all times when RCS temperature is greater than 160 F.
Valves full stroke closed on initiation and cannot be partial-stroke exercised.
Alternate Testing:
Exercise, time, and fail at cold shutdown when all reactor coolant pumps are secured.
O 03851 III-1-22-8 REV. O
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FNP-1-M-042-
?
COLD SHUTDOWN TEST JUSTIFICATION 3,,N.
/.
QlP19-CS-1 l
l System:
Instrument Air Valve:
HV3611 l
i Category:
A Class:
2 ASME Section XI Quarterly' Test Requirements:
Exercise, time, and fail.
Cold Shutdown Test Justification:
Instrument air supplies a number of 1
components inside containment which are I
necessary>for normal operation.
Te s ting during normal. operation.would deprive these. components of their normal air supply, and since the system has no
_' reserve air: storage capacity, could result in operating transients and a f}
possible forced plant shutdown.
Quarterly Part Stroke Testing:
Valves are equipped with full-stroks-
)
only operators and cannot be partial-stroke exercised.
Cold Shutdown Testing:
Exercise, time, and fail at cold shutdown when the normal instrument air can be isolated without causing loss of instruments and components necessary for normal plant operations.
l 03891 III-1-24-2 REV. O L___
}*,
FNP-1-M-042
(}
RELIEF REQUEST Q1P19-RV System:
Instrument Air Valve QV002, QV004
' Category:
AC Class:
2 Function:
Containment isolation simple check' valve (reverse-flow closure for containment
-isolation only).
' ASME Section XI Quarterly. Test?
Requirements:
Verify reverse-flow closure.
Basis for Relief:
The only method available to verify reverse-flow closure is by valve leak testing during Appendix J, Type C,
- testing at refueling.
)-
Alternate Testing:
Reverse-flow closure will be verifded during Appendix J, Type C, testing at refueling.
=
9 1
0389I III-1-24-3 REV. O I
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FNP-1-M-042 RELIEF REQUEST QIR43-RV-1 System:
Diesel Generator Air Start Valve:
QV519, QV520, QV582, QV583, QV638, QV639, QV640, QV641 Category:
B Class Function:
Diesel Generator air start solenoids.
ASME Section XI' Quarterly Test Requirements:
Measure stroke time.
Basis for Relief:
These are three-way solenoid valves mounted on the diesel generator (DG) skid mounted package.
They are in the DG air start line between the air receiver tanks and the air start
. manifolds.
Since each generato'r has two tanks and two manifolds, the DG inay Ig]
start on air supplied by either or both tanks.
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of these valves independently on an alternating basis by isolating one air start header and starting the DG from one header at a tims.
Stroke time cannot be measured because there are no position indicators and visual observation is not possible due to valve design.
The total time from initiation to DG operation is measured such that in effect each valve's stroke time is verified as acceptable.
The DG start test is performed more frequently than required by Section XI so that actual valve testing criteria is more limiting than Section XI requirements.
l-Alternate Testing:
These valves will be te'ted as part of s
the diesel generator air start test.
Acceptable diesel generator start time will be used to verify valve operability and acceptable stroke time.
O 0428I III-1-26-4 REV. 0
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ENCLOSURE 3 g
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IN SEP B Gf W8Stinghouse PowerSystems Enee systems ac.
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Electric Corporation 9
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Box 355 8
Pmsburgh Pennsylvania 15230 0355 ALA-774, Rev. 1 S. O. ALA-280 FRSSS/SS-ALA-5004 September 25, 1987 Mr. W. G. Hairston 111, Vice President Alabama Power Company 600 North Eighteenth Street Birmingham, AL 35291-0400 JOSEPH M. FARLEY NUCLEAR PLANT UNITS NO. 1 AND 2 ISI TESTING l
Dear Mr. Hairston:
Per APCo letter NMS-87-0558 Westinghouse was requested to evaluate full flow testing of 23 check valves located in the high and low head safety injection system. Specifically, the NRC questioned the ability of existing test procedures to verify that certain valves can be stroke tested as required by ASME Section XI. Westinghouse has been requested to evaluate the existing system design and develop a technical justification for using the existing surveillance tests as a credible means of assuring that each valve in the system has not degraded to an unacceptable level.
The' design criteria of the existing ECCS considers both total pump flowrates as well as flow distribution.
The Farley accident analyses have assumed certain i
high and low head branch line flowrates which must be met to support the
)
analyses. This is the reason why the individual HHSI cold leg branch lines are l
set to 1193 GPM as required by Technical Specification 3/4.5.2.
During Pre-Op
{
testing flowrates of all HHSI bra.1ch lines were set using throttle valves to a l
pre-set value.
In addition the applicable LHSI flowrates were also verified.
The concern expressed by the NRC is that a check valve might fail to open, or to only open partially.
If this did occur, branch line flowrate could be reduced to an unacceptable level. The issue is whether existing plant test procedures will provide sufficient Indication of low branch line flowrate.
l 9395e e
1
.e ALA-774, Rev. 1 S. O.'ALA-280 FRSSS/SS-ALA-5004 Mr. Hairston September 25, 1987 1
This study included two parts;.1) evaluation of valve operating history from discussions with valve vendors and a review by Westinghouse Reliability-Engineering, and 2) system performance and sensitivity evaluation..it is noted l
that of the 23 valves in question, 12 are 2" Kerotest valves and the remaining are 6" Velan swing check valves.
After reviewing documented failures for Kerotest 1/2"- 2" check valves, it was j
determined that excessive seat leakage was the failure mode for the majority of cases. Only.one case identified was a result of disc sticking. This was due to rust and corrosion within a carbon steel valve. This should not be a problem since the Farley Units use stainless steel valves, not carbon steel.
The vendor was also contacted for information on sticking problems. Although i
some of their models (series 3000) did have some problems with sticking in the past, the 9000 series model which applies to Farley Units 1 and 2 has had no such problem.
In reference to the 6" Velan swing check valves the following information was g
identified. Review of the reliability data plus discussions with Velan q
indicated there was a problem with the swing check valves sticking open due to the dise lock wire getting lodged between the disc and body. The problem was addressed in IE Hotice 81-30 which identified the potential problem with the valves and requested that the utilities evaluate the problem. Since the 1
bulletin was issued and the change made to the valves affected there has not been any reported problem of the valves being stuck open.
It is also noted that this type of failure could be easily detected when performing the valve leak rate test.
i l
I The sensitivity evaluation developed a model of the current low head and high l
head safety injection systems to determine the impact valve binding has on 1) the total injected flowrate, and 2) the requirement for the individual branch line flowrates. The available margin was identified by comparing flowrates i
established during Pre-Op testing versus the flowrates assumed in the current I
accident analysis.
j 1
l 9395e 1
1
7-w c.
- A
',r ALA-774, Rev.1 S. O. ALA-280 FRSSS/SS-ALA-5004-Mr. Nairston September; 25, 1987 I.
+
t For the sake of'this discussion the 23 valves will be grouped into the following 4 categories:
t
/
Group 1 Group 2 Group 3 Group 4 1-8990A,8,C 1-8973A,B,C 1-8998A,8,C 1-8988A,B
- 1-8992A,B,C 1-8993A,B.
1-8993C 1-8995A,B,C-1-8997A,B,C i
Group 1.
Group 1 consists of valves located in the high head safety injection system.
Flowrate through each of these check valves is solely from the NHSI/CHG pumps.
l i
Normal full flowrate through these valves is set at approximately 200 gam. At this flowrste the valve.is opened to about 70% of full valve lift (except for, the 6" valve 8993C which would be opened significantly less due to its larger size).
i For this group of valves the sensitivity evaluation determined that if one.
check valve failed to open the total flowrate which could be expected from one j
CHG pump with the two other branch lines delivering is 1500 GPM. Given that the acceptance criteria for surveillance test FNP-1-STP-40 is 1600 GPM, this procedure would adequately detect valve failure, in addition, the sensitivity evaluation determined that due to available margin the system can still meet its design criteria even if the valve only opens to 35% of full valve stroke (again, except for valve 8993C which is not required to open as much).
1 1
1 9395e
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4-
- 4
't1 ALA-774,-Rev.O 1 S. O. ALA-280 FRSSS/SS-VA-5004 Mr. Hairston September' 25,1987
/
Group 2<
q tGroup 2 consists of valves located in the low head safety injection system.
Flowrate through each_of these valves is solely from the RHR pumps. Normal ECCS flowrate.through1these valves is 1350 GPM. At this flowrate these valves are expected to be full _open.
i
'If one check valve _ failed to open"during surveillance test FNP-1-STP-40 the maximum achievable pep flowrate would be about 3500 GPM. The acceptance criteria is for a flowrate 13981 GPM; therefore, this test would also be able to detect valve failure.
in addition, our evaluation determined that tho'v system can meet its design. criteria even if the valve only opens to 45% of its full stroke.
A Group 3-This group consists of those valves which are shared between the LHSI and the NHSI systems. Normal ECCS' full flowrate through these valves is approximately 1550 GPM. At this flow the valves are normally full open.
The impact of one of these valves falling to ope would have the combined effect-of the failures discussed for group 1 and 2 valves. Total LHSI and NHSI flow would drop to about 3500 GPM and 1500 GPM respectively. Similar to the other groups even with these valves only partially opened the system can still meet the design requirements.
Group 4 These valves are located in the LHSI hot leg injection flow paths. These flow paths are only aligned during hot leg recirculation. Valves 8988A,B only pass LHS1 flow while 8993A,B pass both low head and high head flowrate.
l i
9395e
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ALA-774, Rev.1 S. 0..ALA-280 9'
FRSSS/SS-ALA-5004-Mr. Hairston-September 25, 1987' I
5 (s
.' Group 4..(continued)
- 1 The ECCS design basis requirement during the hot leg recirculation phase is l
that sufficient flow be provided to the core to maintain' inventory which is lost due to boil-off. All available sources can be taken credit'for.(LHSI and HHSI) and there are no specific requirements for flow balancing. The present analysis calculating the time required to go to hot leg recirculation (11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />) demonstrates that with one train operating and one line spilling, sufficient flow is injected from the NHSl pumps to satisfy flow requirements.
As such, there is no requirement for LHSI flow; therefore, valves 8988A,8 could fall close without any impact on safety.
t Failure of valves 8993A,B wiII have the same impact on HHSI fIow as those failures identified for Group 1.
If one of these valves.falled to open the total CHC flowrate would be 1500 GPM.-
The same as for Group 1, the acceptance criteria for surveillance test FNP-1-STP-40 is 1600 GPH; therefore, failure of the valve to open could be detected.
j in summary, Westinghouse believes that given the operating history and the results of the technical evaluation, the current test procedures provide adequate assurance that the check valves will perform properly. As such we do not support the need to add additional flow indication to each branch line, or to disassemble valves to determine acceptable performance.
Very truly yours, WESTINGHOUSE ELECTRIC CORPORATION i
C. Eicheidinger, Manager Alabama Project R.D.Magee/jb cc:
R. P. Mcdonald 1L W. G. Hairston til 1L J. D. Woodard 1L K. C. Gandhi 1L L. B. Long 1L J. R. Crane 1L R. H. Baulig 1L (W Farley Site)
' R. W. Wise 1L Y
9395e
i..
f ENCLOSURE 2
-OLD RELIEF NEW RELIEF
_ VALVE NUMER REQ. NO.
APPROVAL DOCUENT & DATE REQ. NO.
4 RCS - TPMS Q1B13 QV038. 1-8046 3.1.3 SER 05/02/83 RV-2 QV054 1-8092 3.1.3 SER 05/02/83 RV-2 LHSI/RHR - TPMS Q1E11 QV001A 1-8701A 3.1.8 TECH SPEC AMEND 50 CS-1 SER 05/02/83 QV001B 1-8702A 3.1.8 TECH SPEC AMEND 50 CS-1 SER 05/02/83 QV016A 1-8701B 3.1.8 TECH SPEC AMEND 50 CS-1 SER 05/02/83 QV016B 1-8702B 3.1.8 TECH SPEC AMEND 50 CS-1 SER 05/02/83 QV021A 1-8973A 3.1.12' TECH SPEC AMEND 50 RV-2 SER 05/02/83
.QV021B 1-8973B 3.1.12 TECH SPEC AMEND 50 RV-2 SER 05/02/83 QV021C 1-8973C 3.1.12 TECH SPEC AMEND 50 RV-2 l
SER 05/02/83 QV025A 1-8811A 3.1.23 TECH SPEC 01/26/84 RV-1 QV025B 1-8811B 3.1.23 TECH SPEC 01/26/84 RV-1 QV042A 1-8974B 3.1.12 TECH SPEC AMEND 50 RV-2 SER 05/02/83 QV042B 1-8974A 3.1.12 TECH SPEC AMEND 50 RV-2 SER 05/02/83 QV044 1-8889 3.1.17 SER 05/02/83 CS-2 QV051A 1-8998A 3.1.13 SER 05/02/83 RV-3 QV051B 1-8998B 3.1.13 SER 05/02/83 RV-3 QV051C 1-8998C 3.1.13 SER 05/02/83 RV-3 CS - TPMS Q1E13 QV003A 1-8826A 3.1.23 SER 01/26/84 RV-2 QV0038 1-8826B 3.1.23 SER 01/26/84 RV-2 Page 1
OLD RELIEF NEW RELIEF l
VALVE NUf8ER REQ. NO.,
APPROVAL DOCUMENT & DATE REQ. NO.
CONTAINMENT ISOLATION - Q1E14 QV001 3.1.3 SER 05/02/83 RV-1 QV002:MOV-3660 3.1.27 SER 05/02/83 CS-1 QV003 MOV-3318A 3.1.28-SER 05/02/83 CS-1 QV004 MOV-3318B 3.1.28 SER 05/02/83 CS-1 HV-3657 3.1.27 SER 05/02/83 CS-1 HV-3658 3.1.27 SER 05/02/83 CS-1 sI/CVCS - Q1E21 QV026 1-8926 3.1.14 SER 05/02/83 RV-1 QV032A 1-8948A 3.1.15 TECH SPEC AMEND 50 RV-2 NRC LETTER 11/15/84 QV032B 1-8948B 3.1.15 TECH SPEC AMEND 50 RV-2 NRC LETTER 11/15/84 QV032C 1-8948C 3.1.15 TECH SPEC AMEND 50 RV-2 NRC LETTER 11/15/84 QVCL7A 1-8956A 3.1.34 TECH SPEC AMEND 50 RV-2 NRC LETTER 11/15/84 SER 05/02/83 QV037B 1-8956B 3.1.34 TECH SPEC AMEND 50 RV-2 NRC LETTER 11/15/84 l
SER 05/02/83 QV037C 1-8955C 3.1.34 TECH SPEC AMEND 50 RV-2 NRC LETTER 11/15/84 SER 05/02/83 1
QV052 1-8861 3.1.35 SER 05/02/83 RV-3 I
QV058 1-8947 SER 05/02/83 RV-3 i
QV062A 1-8897A 3.1.14 SER 05/02/83 RV-4
)
QV062B 1-8897B 3.1.14 SER 05/02/83 RV-4 QV062C 1-8897C 3.1.14 SER 05/02/83 RV-4 QV063 1-8885 3.1.25 SER 05/02/83 RV-5
)
QV066A 1-8995A 3.1.2 SER 05/02/83 RV-6 QV066B 1-8995B 3.1.2 SER 05/02/83 RV-6 QV066C 1-8995C 3.1.2 SER 05/02/83 RV-6 1
QV068 1-8886 3.1.25 SER 05/02/83 RV-5 i
QV072 1-8884 3.1.25 SER 05/02/83 RV-5 QV076A 1-8988A 3.1.1 TECH SPEC AMEND 50 RV-10 SER 05/02/83 QV076B 1-89888 3.1.1 TECH SPEC AMEND 50 RV-10 SER 05/02/83 QV077A 1-8993A 3.1.36 TECH SPEC AMEND 50 RV-11 SER 05/02/83 QV077B 1-8993B 3.1.36 TECH SPEC AMEND 50 RV-11 SER 05/02/83 l
Page 2
]
a
OLD RELIEF NEW RELIEF VALVE NUMBER REQ. NO.
APPROVAL DOCUMENT & DATE REQ. NO.
-QV077C 1-8993C 3.1.36-TECH SPEC AMEND 50 RV-11 SER 05/02/83-QV078A'1-8990A 3.1.2 SER 05/02/83 RV-6
. Q)'078B 1-8990B 3.1.2 SER 05/02/83 RV-6 QV078C 1-8990C 3.1.2 SER 05/02/83 RV-6' QVU79A 1-8992A 3.1.2 SER 05/02/83 RV-6 QV079B 1-8992B 3.1.2 SER 05/02/83 RV-6 QV079C 1-8992C 3.1.2 SER 05/02/83 RV-6
-QV115A 1-8368A 3.1.3 SER 05/02/83 RV-3 QV115B 1-8368B 3.1.3 SER 05/02/83 RV-3 z
QV115C 1-8368C 3.1.3 SER.05/02/83 RV-3 QV119 1-8381 3.1.3 SER 05/02/83 RV-3 i
QV210 '1-8442 3.1.41' SER 05/02/83 CS-2 1
l
-QV213 1-8103 3.1.3 SER 05/02/83 RV-3' QV253A 1-8149A 3.1.50 SER 05/02/83 CS-1 QV253B 1-8149B 3.1.50 SER 05/02/83 CS-1 e
.QV253C 1-8149C 3.1.50 SER 05/02/83 CS-1 QV254 1-8152 3.1.19 SER 05/02/83 CS-3 QV257 1-8107 3.1.19 SER 05/02/83 CS-3
-QV258 1-8108 3.1.19 SER 05/02/83 CS-3 QV264 1-8104 3.1.37 SER 05/02/83 CS-2 QV326A 1-8132A 3.1.48 SER 05/02/83 RV-9 QV326B 1-8132B 3.1.48 SER 05/02/83 RV-9 QV327A 1-8133A 3.1.48 SER 05/02/83 RV-9 QV327B 1-8133B 3.1.48 SER 05/02/83 RV-9
)
QV336A LCV115B 3.1.51 SER 05/02/83 CS-4 QV336B LCV115D 3.1.51 SER 05/02/83 CS-4 I
QV376A LCV115C 3.1.19 SER 05/02/83 CS-4 QV376B LCV115E 3.1.19 SER 05/02/83 CS-4 LIQUID WASTE DISPOSAL - TPMS Q1G21 QV204 3.1.3 SER 05/02/83 RV-1 QV291 3.1 3 SER 05/02/83 RV-1 MAIN STEAM - TPMS Q1N11 QV003A HV3368A 3.1.22 SER 05/02/83 CS-2 QV003B HV3368B 3.1.22 SER 05/02/83 CS-2 QV003C HV3368C 3.1.22 SER 05/02/83 CS-2 QV003D HV3976A 3.1.22 SER 05/02/83 CS-2 QV003E HV3976B 3.1.22 SER 05/02/83 CS-2 i
QV003F HV3976C 3.1.22 SER 05/02/83 CS-2 Page 3
..l OLD RELIEF NEW RELIEF VALVE NUpBER REQ. NO.
APPROVAL DOCUMENT & DATE REQ. NO.
FEEDWATER - TPMS Q1N21 QV001A M0V3232A 3.1.24 SER 05/02/83 CS-1 QV0018 M0V3232B 3.1.24 SER 05/02/83 CS-1 QV001C MOV3232C 3.1.24 SER 05/02/83 CS-l' AUXILIARY FEEDWATER - TPNS Q1N23 QV002A 3.1.5 SER 05/02/83 CS-1 QV002B 3.1.5 SER 05/02/83 CS-1 QV002C 3.1.5 SER 05/02/83 CS-1 QV002D 3.1.5 SER 05/02/83 CS-1 QV002E 3.1.5 SER 05/02/83 CS-1 QV002F 3.1.7 SER 05/02/83 CS-1 QV002G 3.1.5 SER 05/02/83 CS-1
.QV002H 3.1.7 SER 05/02/83 CS-1 QV003 3.1.7 SER 05/02/83 CS-1 QV006 3.1.43 SER 05/02/83 CS-1 QV007A 3.1.44 SER 05/02/83 CS-1 QV007B 3.1.44 SER 05/02/83 CS-1 QV011A M0V3350A 3.1.5 SER 05/02/83 CS-1 QV011B MOV3350B 3.1.5 SER 05/02/83 CS-1 QV011C M0V3350C 3.1.5 SER 05/02/83 CS-1 I
QV013A MOV3210A 3.1.6 SER 05/02/83 RV-2 QV013B M0V3210B 3.1.6 SER 05/02/83 RV-2 1
l QV014A M0V3209A 3.1.6 SER 05/02/83 RV-2 l
QV014B M0V3209B 3.1.6 SER 05/02/83 RV-2 QV014C M0V3216 3.1.6 SER 05/02/83 RV-2 l
l DEMINERALIZED WATER - TPNS Q1P11 1
j QV002 3.1.3 SER 05/02/83 RV-1 CONTAINMENT PURGE - TPNS Q1P13 i
QV281H V31980 3.1.45 SER 05/02/83 CS-1 QV282H V3197 3.1.45 SER 05/02/83 CS-1 QV283H V3196 3.1.45 SER 05/02/83 CS-1 QV284H V3198A 3.1.45 SER 05/02/83 CS-1 l
i Page 4 l
L
~
OLD RELIEF NEW RELIEF VALVE NUMER-REQ. NO.
APPROVAL DOCUMENT & DATE REQ. NO.
SERVICE WATER - TPNS'Q1P16 i
QV043A M0V3024A 3.1.52 SER 05/02/83 CS-2 QV043B M0V3024B 3.1.52 SER 05/02/83 CS-2 QV043C M0V3024C 3.1.52 SER 05/02/83 CS-2 QV043D M0V3024D 3.1.52 SER 05/02/83 CS-2 QV071 M0V3135 3.1.11 SER 05/02/83 RV-1' QV072 M0V3134 3.1.11 SER 05/02/83 RV-1 QV075 3.1.3 SER 05/02/83 RV-2 QV081 MOV3131 3.1.11 SER 05/02/83 RV-1 QV514 3.1.53 SER 05/02/83 CS-1 QV515 3.1.53 SER 05/02/83 CS-1 QV516 3.1.53 SER 05/02/83 CS-1 QV517 3.1.53 SER 05/02/83 CS-1 CCW - TPNS Q1P17 QV082 MOV3052 3.1.20 SER 05/02/83 RV-1 QV083 3.1.3 SER 05/02/83 RV-2 QV097 M0V3046 3.1.20 SER 05/02/83 RV-1 QV099 MOV3182 3.1.20 SER 05/02/83 RV-1 QV159 3.1.3 SER 05/02/83 RV-2 HV3045 3.1.20 SER 05/02/83 RV-1 HV3067 3.1.46 SER 05/02/83 RV-4 HV3095 3.1.46 SER 05/02/83 RV-4 HV3184 3.1.20 SER 05/02/83 RV-1 HV3443 3.1.46 SER 05/02/83 RV-4 INSTRUMENT AIR - TPNS Q1P19 QV002 3.1.3 SER 05/02/83 RV-1 QV004 3.1.29 SER 05/02/83 RV-1 SER 01/26/84 HV3611 3.1.21 SER 05/02/83 CS-1 Page 5
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