ML20078F667
| ML20078F667 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/05/1983 |
| From: | Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM JPN-83-85, NUDOCS 8310110112 | |
| Download: ML20078F667 (18) | |
Text
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123 Wn Ctreat Wheto I'latns, New York 10001 914 68tG240
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& Authority october 5, 1983 Nuciear cenmuon JPN-83-85 Director of Nuclear Reactor Regulation U.
S. Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Mr. Domenic B. Vassallo, Chief Operating Reactor Branch No. 2 Division Of Licensing
Subject:
James A.
Fitzpatrick Nuclear Power Plant Docket No. 50-333 NUREG-0737 Item II.B.3 Pcst-Accident Sampling System
References:
1.
NRC letter, D.
B. Vassallo to L. W.
Sinclair, dated July 27, 1982.
2.
NYPA letter, J.
P.
Bayne to D.
B. Vassallo, dated November 16, 1982 (JPN-82-83).
3.
NYPA letter, J. P.
Bayne to D.
B. Vassallo, dated August 5, 1983 (JPN-83-72).
4.
NEDC-30088, " Responses to NRC Post-Implementation Review Criteria for Post-Accident Sampling Systems", dated April, 1983.
Dear Sir:
As discussed in References 1 and 2, to this letter provides the Phase I responses for Criteria 1, 2d, 3, 6, lla, and llb for NUREG - 0737 Item II.B.3. for the post-implementation review of the Fitzpatrick Post Accident Sampling System.
The remaining responses will be submitted 6 months after this submittal.
If you have any questions, please contact Mr. J.
A. Gray, Jr. of my staff.
Very truly yours, O
ExecutiveVic}ePresident J.
P'.
Bayri Nuclear Generation cc:
Office of the Resident Inspector U.S. Nuclear Regulatory Commission P.O.
Box 136 o
Lycoming, NY 13093 0
8310110112 831005 DR ADOCK 05000333 PDR
VM NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT JPN-83-85 ATTACHMENT 1 Criterion: (1)
The licensee shall have the capability to promptly obtain reactor coolant samples and containment atmosphere samples.
The combined time allotted for sampling and analysis should be 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> or less feom the time a decision is made to take a sample.
~-
Response
(1)
The James A. FitzPatrick Nuclear Power Plant has the capability to obtain a liquid sample within the required 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
The longest run of piping for the liquid sample is the RHR line, totaling about 625 feet.
To assure that the sample is representative of actual plant conditions, the time to draw the sample was estimated assuming 3 full volumes circulate through the sample station.
This sample time is about 10 minutes with a 1 gpm flow.
Contingent upon completion of items identified in Reference 3, the Plant will have the capability to obtain dissolved gas samples of the primary coolant. The Plant has the capability to obtain a primary containment atmosphere sample.
This sample, with a 210 foot run at 18 SCFH can be taken in about 3 minutes.
The sample station, supplied and designed by General Electric Company, has been installed in the Recirculation M-G Set Room adjacent to the Reactor Building on Elevation 300'.
The control panel is about 2 feet away and perpendicular to the sample station.
The main transport route of the sample cask in accident conditions, shown in Figure 1, would be from the Recirculation M-G Set Room through the Administration Building and down the elevator to the chemistry lab, located between the Turbine & Reactor Buildings on Elevation 272' where the samples are analyzed.
The total travel distance on this route is approximately 330 feet.-
_ - ~.
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Shielded casks are provided at the plant for transporting the liquid and gascous samples to the chemistry lab.
The sample panel and its associated solenoid operated valves (SOV's) are powered through the normal 120V AC supply.
In the event of a loss of of f-site power, the alternate power supply is a 600V emergency bus powered by the emergency
~
diesel generator.
Contract arrangements have been made with Babcock & Wilcox for all off-site analyses.
The FitzPatrick plant will use the shipping cask, being procured by the
~
Pooled Inventory Management (PIM) organization, which will be located at their Memphis, Tennessee warehouse for off-site shipments.
The following is a breakdown of the times for obtaining, handling, and analyzing a sample:
a.
obtain the sample i.e.
(recirculate line, install vial and operate the control panel) 60 min J
b.
transport sample to lab 15 min 1
c.
sample preparation 20 min
.d.
sample analysis 80 min Criterion:
(2d) Alternatively, have in-line monitoring s
capabilities to perform all or part of the above analyses.
Response
(2d) The GE PASS employed at FitzPatrick only uses a grab sample system.
The only in-line capability is a conductivity indicator which can be used to perform
~ all or part of the analysis for boron
~
o concentration.
A solumeter used with an
. appropriate conductivity cell can perform this but will not be used to meet the criterion of NUREG-0737.
Criterion:
(3)
Reactor coolant and containment
, atmosphere sampling during post accident conditions shall not require an isolated auxiliary system [e.g.,
the letdown
^
system, reactor water cleanup (RWCUS)] to be placed in operation in order to use the sampling system.
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Response
(3)
The use of an isolated auxiliary system is not required for the PASS to sample reactor coolant and containment atmosphere during post-accident conditions.
The RHR (Residual Heat Removal) liquid l
sample lines tap into the discharge line of the RHR system shown in Figure 2.
This system must be in operation in order i
l to obtain a pressurized samplc.
No auxiliary system is needed to take this sample.
Jet pump liquid sample lines tap into the downstream side of the excess flow check valves in the jet pump instrument lines of pumps 7 and 15, shown in Figure 3.
The samples are circulated at j
approximately 1/2 to 1, gpm, so the excess flow check valve will not close unless there is a break in the line.
Recirculation pumps are not needed, and no auxiliary system is needed for this sample.
There is a common return line that goes from the liquid sampling station directly l
to a torus penetration, shown in Figure 4.
This again needs no auxi-liary-system for returning or recirculating the sample coolant, and is not affected by post-accident operation.
The gas samples are obtained from the primary containment, torus and secondary containment as marked on Figures 5,6 and 7.
The common return line, Figure 8, goes back to the torus.
No auxiliary system is necessary to draw the gas sample.
Vacuum pumps are located in the gas sample station and are used to obtain the samples.
The PASS valves which are not accessible after an accident but are required to operate the sampling system, have been incorporated in the environmental qualification program for FitzPatrick.
The solenoid operated valves (SOV's) which serve as redundant isolation valves, have been analyzed in the Authority's I&E Bulletin 79-OlB report for the' FitzPatrick Plant.
Although these SOV's would normal.ly close on a containment isolation signal, they may be opened after an accident at the primary containment purge panel (in the relay room) by use of keylocked switches if a sample needs to be taken.
The manual globe valves associated with the RHR sample lines are normally open, and are part of a Cat. 1 system, therefore they only need to be seismically qualified, which they are.
Criterion:
(6)
The design basis for plant equipment for reactor coolant and containment atmosphere sampling and analysis must assume that it is possible to obtain and analyze a sample without radiation exposures to any individual exceeding the criteria of GDC 19 (Appendix A,
Response
(6)
Adequate design has been provided at FitzPatrick to obtain and analyze a post accident sample without exceeding personnel radiation exposure limits of 5 rem whole body and 75 rem to the extremities (GDC 19).
Table 2,
" Expected Dos e Ra te s ", is based on Reg. Guide 1.4 source terms and NEDC-30088 (Ref. 4) values for dose rates from the casks and sample station.
Plant specific values have been calculated using a correction factor to incorporate the different core inventories at FitzPatrick (Table 1) versus the generic plant (NEDC-30088)
Ref. 4.
In Table 2 the times shown are the actual times the body or extremity is being exposed and not the entire time required for each particular task.
Criterion:
(11) In the design of the post accident sampling and analysis capability, consideratica should be given to the following items:
(a)
Provisions for purging sample lines, for reducing plateout in sample lines, for minimizing sample loss or distortion, for preventing blockage of sample lines by loose material in the RCS or containment, for appropriate disposal of coolant loss from a rupture of the sample line.
The post accident reactor coolant and containment atmosphere samples should be representative of the reactor coolant in the core area and the containment atmosphere following a transient or accident.
The sample lines should be as short as possible to minimize the volume of fluid to be taken from containment. _.
The residues of sample collection should be returned to containment or to a closed system.
(b)
The ventilation exhaust from the sampling station should be filtered with charcoal absorbers and high-efficiency particulate air (HEPA) filters.
Response: (lla)
The gas lines are heat traced to prevent condensation and minimize plateout.
The design of the heat tracing system utilizes Thermon's type SSK heating cable.
Thermon's solid state control i
system is used for controlling the heat tracing wich temperature and current i
alarm functions.
J From the analysis for Criterion 1, it can be shown that the purge velocity for the entire PASS system is approximately 180 ft./ min.
The PASS lines shall be purged a
subsequent to each use.
This will also
~
reduce plateout thereby minimizing distortion of the sample results.
The use of restricting orifices was eliminated to prevent blockage of sample lines by loose material in the RCS or containment.
Solenoid operated shut-off valves and reduced line size (1/2" tube) i~ -
limit reactor coclant loss from a rupture of the sample line.
The sample lines have been designed as short as possible to minimize the volume of fluid to be taken from the containment.
i The FitzPatrick PASS system was designed to take reactor coolant and suppression chamber samples that are representative i
of actual core conditions both short and long term.
The primary sample point is the jet pump discharge line which would be used for large or small breaks as long as a sample could be drawn.
While maintaining nearly normal water level, natural circulation would occur with flow i
from downc'omers to the shroud area through the jet pumps.
This would force flow past the PASS sample tap and allow a sample to be taken which will be used to evaluate to the actual core conditions.
i In a large break condition in which normal water level cannot be maintained, water level is controlled by the height of the jet pumps.
In this case, the RHR-LPCI pumps would supply coolant via 1
.---,.,-.--,.,,,-.n,..
.v-,,..,._,.,.-
n.. -., -. - - -
--,.c.-
.-.,,,._n.,
'O the recirculation line to the core, up through the jet pumps and out the break (i.e. recirculation pump suction break).
This would again provide flow directly from the core to the sample point.
As reactor pressure decays, the sample point at the jet pump discharge may not have enough pressure to draw the sample, so the RHR pump discharge would have to be utilized.
This water is from the torus and at first would not be representative of core conditions.
As time progresses the reactor coolant will be recirculated to the torus, and a more representative sample of actual core conditions could be analyzed.
(llb)
A dedicated sample exhaust filtration system has been installed which has a HEPA filter in series with a charcoal absorber and another HEPA filter whose exhaust leads to the turbine building ventilation system.
In Figure 9 the filter arrangement as well as a flow diagram of the entire PASS system is shown.
s Table 1 CORE INVENTORY OF MAJOR FISSION PRODUCTS IN THE FITZPATRICK PLANT OPERATED AT 2436 MWt FOR THREE YEARS Inventory 6
Chemical Group Isotope Tl/2 (10 Curies)
Noble Gases Kr-85m 4.48h 16.4 Kr-85 10.72y 0.73 Kr-87 76.30m 31.4 Kr-88 2.84h 44.6 Xe-133 5.25d 134.8 Xe-135 9.11h 17.4 Halogens I-131 8.04d 64.1 I-132 2.30h 93.4 I-133 20.80h 134.1 I-134 52.60m 147.4 I-135 6.61h 126.1 Alkali Metals Cs-134 2.06y 13.1 Cs-137 30.17y 8.1 Cs-138 32.20m 1973.
Noble Metals Mo-99 66.02h 122.1 Ru-103 39.40d 103.4 Alkaline Earths Sr-91 9.50h 76.7 Sr-92 2.71h 82.1 Ba-140 12.8 d 115.4 Rare Earths Y-92 58.6 d 82.7 La-140 40.20h 122.8 Ce-141 32.50d 107.4 Ce-143 284.30d 86.1 Refractories Zr-95 64.00d 107.4 Zr-97 16.90h 110.8, _ _ _. _ _ _
Table 2 EXPECTED DOSE RATES (1 hr. after accident)
Notes: E = Extremity doses calculated at 10cm.
W = Whole body doses calculated at 60cm.
- l. Liquid Sample Time
Background
Sample Dose Integdose (min)
(mr/hr)
(mr/hr)
(mr)
(W) obtain sample 10 99 93 32.0 (E) handle sample
.5 99 1,300 11.7 (W) transport cask 10 45.8 5.7 8.6 (W) sample preparation 6
99 240 33.9 (E) sample preparation 4
99 79,200 5,286.6 (W) sample analysis 8.5 (Boron) 99 44 20.3 (E) sample analysis 1.5 (Boron) 99 1,580 39.5 1
(W) cample analysis 20 (isotopic) 99 33
)
2.
Gas Sample (W) obtain sample 10 99 300 66.5 (W) handle sample 1
99 350 7.5 (W) transport cask 10 44.6 45 14.9 (E) transport cask 10 44.6 2,000 340.8 (W) sample preparation 6
99 520 61.9 (E) sample preparation 4
99 186,000 12,466.0 (W) sample analysis 30 (Hydrogen) 99 18.5 58.8 (E) sample analysis 1.5 (Hydrogen) 99 186,000 4,652.5 (W) sample analysis 20 (isotopic) 99 33 Total integrated whole body dose for liquid sample =
127.8 mr Total integrated whole body dose for gas sample 242.6 mr
=
Total integrated whole body dose for samples 370.4 mr
=
Total integrated extremity dose for liquid samples =
5,337.8 mr 17,459.3 mr Total integrated extremity dose for gas sampics
=
Total integrated extremity dose for samples 22,797.1 mr i -
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