ML19318A381
| ML19318A381 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 06/12/1980 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| TASK-06-04, TASK-6-4, TASK-RR LAC-6982, NUDOCS 8006200420 | |
| Download: ML19318A381 (20) | |
Text
.u-0 DA/RYLAND h
fYfCOOPERATIVE va aox sti usss="
mt
+.
.r June 12, 1980 In reply, please refer to LAC-6982 DOCKET NO. 50-409 Director of Nuclear Reactor Regulation ATTN:
Mr. Dennis L.
Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors U.
S. Nuclear Regulatory Commission Washington, D.
C.
20555
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DDR-45 CONTAINMENT PURGING AND VENTING DURING NORMAL OPERATION
Reference:
(1)
NRC Letter, Ziemann to Linder, dated October 23, 1979.
(2)
DPC Letter, Linder to Ziemann, LAC-6815, dated March 6, 1980.
(3)
Allis-Chalmers Report VER-0209, dated December 17, 1979.
(4)
Allis-Chalmers Summary Report, Rev. 02, dated April 10, 1980.
I Gentlemen:
By letter of October 23, 1979 (Reference 1), the NRC requested all licensees of operating reactors to provide the NRC staff with infor-mation which demonstrates that licensees have initiated action to verify containment purge and vent valve operability.
Licensees were requested to demonstrate by test or by test and analysis that contain-ment isolation (ventilation) valves would shut under postulated DBA-1 LOCA conditions.
In order to further confirm the design adequacy of the containment valves, DPC in cooperation with Allis-Chalmers,
)
embarked on a scale model valve qualification test program in l
November, 1979, at Langley Research Center, Pampton, Virginia, y
i i
The series of air dynamic flow tests, the first of this type to be conducted to specifically measure dynamic flow induced forenn on butterly containment ventilation-isolation valves, demonstrated that there is substantial safety margin for operation of the valves durinc postulated design basis accidents.
The A-C test renults and DDC l
Summary Evaluation-of the test results were forwarded tothe NPC in Deference 2 dated March 6, 1980.
The data confirmed that the valves F
THIS DOCUMENT CONTAINS P003 QUALITY PAGES
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L J
Mr. Dennis L.
Ziemann, Chief LAC-6982 Operating Reactors Branch #2 June 12, 1980 will close from a 90 full open position under the most severe postulated LOCA conditions.
Following are answers to additional questions recently posed by NRC personnel and NRC consultants.
1.
NRC Question:
What does the presence of pressure drop in the test intet piping and its effect on the disc dynamic torque measurements have on the conclusions that the valve vill fully close.
DPC RESPONSE:
In Figure lA of Reference (2) (revised copy attached), it can be seen that the minimum margin between the operator supply torque and the valve demand torque occurs either at approximately 10 disc opening or at full closure.
At this small disc opening, the dynamic flow has decreased to the extent that the inlet piping pressure drop is very nearly equal to the supply pressure.
For example, for test No. 31, which is the bases for the data plotted in Fig. lA, the supply pressure from A-C report is given as 30 psig.
The 6P is maximum and dynamic flow is minimum when the disc is at the nearly closed (limiting torque) condition. The upstream inlet piping pressure differential is small (approximately 1.0 psi).
Therefore, pressure drop in the test inlet piping has an insignificant effect on the conclusions that the valve'will clo;e under dynamic flow conditions.
2.
NRC Question:
What is the significance of the flou test resulta uhen the valve diac shaft is oriented "in-plane" uith the intet pipe elbou and 900 "ou t-of-plane " ui th the inlet elbou?
DPC RESPONSE-The "in-plane" and "90 out-of-plane" valve shaft orientation tests represented the lowest and highest torque condition that could be expected if the A-C butterfly wafer valve shafts were installed in those configurations (see A-C Report VER-0209).
When the test valves were installed with the shafts 900 out-of-plane with the pipe elbow, the dynamic demand torque increased by 10-20% at disc openings less than 30 rotation.
At openings 30 and greater, the differences in valve torques were less.
LACBWR's valves are installed 45 out-of-plane and therefore the test data of test 31 (900 out-of-plane) upon which the LACBWR evaluation of operability is based, is conservative.
(:
~
Mr; Dennis L.'Ziemann, Chief LAC-6 982 Operating Reactors Branch #2 Jmm 12, 1980 3.
NRC Question:
What protcotion is offered the valvea by the connecting piping during a DBA?
What effecto vill dynamic flou condition have on integrity of ventilation valve piping supporta?
DPC RESPONSE:
The.two butterfly inlet valves and two exhaust valves are installed in series in the ventilation system in 20" Schedule 20 pipe as shown in the-attached Fig.
2.
Each wafer type valve is clamped between two 20-inch 150 lb. slip-on flanges.
The air duct work is attached to the schedule 20 pipe on the containment side of the valves.
As reported in Reference 2, the calculated collapse pressure of the pipe
(>
400 psig - Ref:
Rourke, 5th Edition) is significantly greater than the maximum LOCA pressure of 50 psig.
The ductwork upstream of the attached piping could collapse, however, from the LOCA pressure.
Numerous dampers, the flow restriction of the ductwork and.the inlet piping geometry would prevent debris from being. carried into the inlet valves.
The ednust valve ductwork contains absolute filters and an exhaust fan with a 20" normally closed recirculation valve.
It is unlikely that the ductwork immediately adjacent to the exhaust valves would collapse since the recirculation. valve automatically opens as the isolation valves close, thus tending to equalize pressure inside of the duct work.
A 1/2" mesh screen at the outlet of the recirculation valve would prevent debris from entering the recirculation pipe.
The pipe to which the valves are attached contain no pipe supports.
However, the,ductwork attached to the piping is supported by hangers or the floor. -The loads imposed on the piping during a dynamic flow conditions at 50 psig building pressure were calculated and found to be ' well within June Code limits.
-(
Reference:
NES Letter Report 5101-623, dated April 17, 1980).
A summary of the piping loads and i
stresses is given below.
Sketches of the Containment Ventilation Valves are shown in Figure 2..
1 PIPE LOADIMG AND STRESSES o
i fN TAKE EXH/. Usr 1
1 dm o
o C u L
l L
-L, 3
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y y
t..
Li c,
e m L
o Mr. Dennis L.
Ziemann, Chief LAC-6982 Operating Reactors Branch #2 June 12, 1980 i
Loads (Lbs)
Stress in Stress in Normal & Upset Pipe' (psi)
Welds (psi)
Allowable,
Pipe Li L2 L3 Stress (psi)
Intake 356 24,311 26,705 4,660 7,700 14,400 Exhaust 314 22,943 18,251 6,300 9,100 14,400
- For Faulted Conditions, Allowable Stress is 28,800 psi.
4.
NRC Quca tion:
.In the chamber of the right-hand air cylinder of the Bettic Operator vented to atmospherc?
DPC RESPONSE:
Yes.
Containment building backpressure will not detrimentally affect operation of the valves (Fig. 1-E).
5.
NRC Question:
What are the environmental qualifications of the CIV calenoid valves and uhat is DPC's preventative maintenance progran for thcae valves?
DPC RESPONSE:
Presently, them are two Asco solenoid valves which are 3/8" 3-way, internal piloted diaphragm valves with seals'and discs of Buna "N",120V A-C.
The coils are continuous duty, molded Class F, 311 F, moisture proof rated for 108 Rads.
Two redundant valves are of Barksdale Class A manufacture, Model 1783 SOAC-2Al molded Class H - 350 F continuous duty with maximum recommended ambient temperature of 150 F (continuous duty).
0 Shorter term ambient temperatures can be tolerated up to 300 F.
During normal ventilating operation, the valves are energized to maintain the CI Valves in an open position.
Upon signal of a con-tainment building pressure of 5 psig or high radiation, the valves de-energize to allow the.CI Valves to close by spring action.
4-
Mr. Dennio L. Zicmann, Chief LAC-6982 Operating Reactors Branch June 12, 1980 The solenoid valves are not required to operate after the LOCA event and will remain in a de-energized condition.
They also fail-safe (de-energize) on loss of electrical power.
The existing solenoid valves are therefore qualified to perform their design function.
The solenoid and CI valves are functionally tested and verified for closure once every two weeks in accordance with the requirements of the LACBWR testing program for radiation monitors.
Class B and C leak pressure tests are performed on the CI valves once each refueling outage to test for seat leaks.
Because of the frequent functicnal testing of the system, the need for repairs or replacement of materials has been promptly identified.
The existing solenoid valves. however, are being replaced with certi-fled seismic and environmentally qualified ASCO valves specifically designed for nuclear plant applications.
The replacement valves are ASCO Model No. NP831654E, 3-way, Class H continuous duty coil, 3/8" pipe and S/8" orifice, 115 volt, 60 cycle AC with NEMA watertight enclosure.
i A preventative maintenance program will be initiated for the CI and solenoid valves which tc :e into consideration the manufacturer's recom-mondations and in-situ performance data.
Until such time as additional in-situ data can be accumulated, elastomeric material components such as
^
seals and o-rings are planned to be replaced at least once each 5 years.
G.
NRC Quention:
What is the basic for the spring cupply torques provided in the
)
Allia-Chalmcro report and DPC's summary evaluation?
What is the acceptance criteria for the allovabic valve shaft torque?
DPC RESPONSE:
The operator spring supply torques were supplied by the manufacturer of the valve operators, Bettis Corporation.
The supply torque curve shown in. Figure 1A applies to the inlet and exhaust valves.
The spring torque values listed in A-C report of February 14, 1980 were for the recirculation valve and hence were conservatively low.
The revised values reflect the isolation valve spring characteristics at LACBWR and are given in the attached A-C Engineering Report, Revision 02, dated April 10, 1980.
The conclusions that the valves will operate as designed remains unchanged.
The acceptance criteria and stresses for the 2.5" diameter valve shaf t disc pins are as follows:
AWWA Shaft Torque Rating = 2,050 ft-lb. 9 design S.F. of 2:1 Maximum valve torque = 1300 f t-lb.
Maximum Allowable Shear Stress = 9,000 psi @ design S.F.
of 2:1 Actual-Shear Stress =
5,084 psi Minimum Shaft Safety Factor = 3.1:1
> design S.F.
of 2:1,
- Mr. Dennio L.
Zicmann, Chief LAC-6982 Operating Racetors Branch #2 June 12, 1980 Pin Connection Shaft to Disc = 2.4:1
> design S.P. of 1.5:1 NOTE:
The above values are taken from A-C report of April 10, 1980 and adjusted for a LACBWR disc thickness-to-diameter ratio of 0.21.
Therefore, the components of the valve shaft are structurally adequate for all postulated operating conditions.
7.
NRC Queation:
What aciamic criteria apply to tha ventilation-icolation va l ve s.?
DPC RESPONSE:
The valves are designed in accordance with American Water Works Assoc-intion Standard C-504 a nd the safety factors therein.
The valves are rated at 150 lb. ASA non-shock shutoff pressure.
The calculated maxi-mum containment pressure is < 50 psig and therefore a large margin of safety exists.
A-C has conducted detailed seismic analyses for similar type valves with no reported degradation of operability.
In addition, the manufacturer of the valve actuators, G.
H.
Bettis Comprny, have seismically tested actuators of similar design to those insta. led at LACBWR (see Response Spectra, Pig. 4).
A comprehensive qualification testing program on a later Model 732C-SR80 actuator (generically similar to LACBWR Model No. 732A-SRS2) was seismically tested to 10 g's using a random biaxial input of suf-ficient force to encompass specified response spectra up to 100 Hz
(
Reference:
Bettis Letter, W.
Reed to C. Angle-DPC, dated March 31, 1980).
The seismic qualification parameters for the SR80 actuators is enclosed (Pigure 4).
The present clastomeric seals installed in the CIV operators (Buna-N) are scheduled to be replaced with seals which are generically equivalent to the seal materials which have been environmentally and seismically qualified by Bettis Company (ethylene propylene).
The similarity of design and the conservative safety factors of the LACBWR valves and actuators indicates the valves will operate as designed during a postu-lated seismic event.
8.
NRC Quention:
Deceribe the mechanical design of the 4" ocnt header valve 55-25-003.
DPC RESPONSE:
The valve is a BSB, 600 psig ASA globe valve with quick opening plug, air-to-open 140 sq. in. Buna-N diaphragm, reverse acting (spring-to-close), 3-15 psi.
The diaphragm and pressure control regulator are vented to atmosphere and therefore spring operation in the closing direction is not affected by building back pressure.
The valve will automatically close on loss of air, high reactor pressure or high containment building pressure.
Its closing action will not be affected by the LOCA environment because of the positive action provided by the spring.
_3_
Mr. Dermis L.
Ziemann, Chief LAC-6982 Operating Reactors Branch #2 June 12, 1980 We hope this letter answers your questions.
If you need additional information, please contact us.
Very truly yours, DAIRYLAND POWER COOPERATIVE gf.4 ".-
,n' J
Prank Linder, General Manager FL: CWA:af cc:
J.
Keppler, Reg. Dir., NRC-DRO III I
1 ACTUATOR RATING c
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