ML20083E705
| ML20083E705 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 12/21/1983 |
| From: | William Jones OMAHA PUBLIC POWER DISTRICT |
| To: | John Miller Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM LIC-83-304, NUDOCS 8312290364 | |
| Download: ML20083E705 (7) | |
Text
-_
l p -- -- -
Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 402/536-4000 December 21, 1983 LIC-83-304 Mr. James R.
Miller, Chief U.
S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Licensing Operating Reactors Branch No. 3 Washington, D.C.
20555
References:
(1)
Docket No. 50-285 (2)
OPPD to ONRR letter dated December 3, 1982 (3)
ONRR to OPPD letter dated January 1, 1983 (4)
OPPD to ONRR letter dated April 15, 1983 (5)
ONRR to OPPD letter dated September 1, 1983
Dear Mr. Miller:
NUREG-0737, Item II.B.3 Post-Accident Sampling System (PASS)
Status Report As requested in a telephone call on November 1, 1983 between Mr.
W.
D. Johnson and Mr.
E.
G.
Tourigny of your staff and Mr.
K.
J.
Morris of the District, attached is a status re-port on the PASS.
The eleven criteria provided in NUREG-0737, Supplement 1, are provided only for convenient refer-ence.
The design capabilities of the PASS have been pre-viously addressed by the District and accepted by the Com-mission.
This letter should not be construed as altering 8312290364 831221 PDR ADOCK 05000285 P
PDR 0
\\
i 45 5124 Employment with Equal Opportumty Male / Female l
f.
Mr. James R. Miller LIC-83-304 Page Two the design capabilities of the PASS, as detailed in the reference correspondence.
Interim provisions which are required until the PASS is declared fully operational are also detailed.
Sincerely, W.
C.
Cones Divisden Manager Production Operations WCJ/DJM:jmm Attachment cc:
Mr. J.
E. Gagliardo, Director Division of Resident Reactor Project
& Engineering Programs U.
S.
Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.
Washington, D.C.
20036 Mr.
E.
G.
Tourigny, Project Manager Mr.
L.
A.
Yandell, Senior Resident Inspector
OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION STATUS REPORT ON POST-ACCIDENT SAMPLING SYSTEM (PASS)
Criterion (1)
The licensee shall have the capability to promptly obtain reactor coolant samples and containment a tmosphere 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 from the time a decision is made to take a sample.
Status The equipment utilized for sampling and analyzing reactor coolant and containment atmosphere has been f unctionally tested to verif y flow paths, flow rates, and analysis capabilities.
With the ex-ception of certain analytical instruments discussed in the status of Items (2)(a), (2)(c), and (10), the PASS is operational and cap-able of performing as previously specified.
Criterion (2)
The licensee shall establish an onsite radiological and chemical analysis capability to provide, within the three-hour time frame established above, quantification of the following:
(a)
Certain radionuclides in the reactor coolant and containment atmosphere that may be indicators of the degree of core damage (e.g.,
noble gases, iodines and cesiums, and non-volatile isotopes);
(b)
Hydrogen levels in the containment atmosphere; i
(c)
Dissolved gases (e.g.,
H2), chloride (time allotted for analysis subject to discussion below), and boron con-l centration of liquids; 1
i (d)
Alternatively, have in-line monitoring capabilities to per-form all or part of the above analyses.
Status The in-line equipment required for the specified analyses is oper-able as follows:
(a)
Isotopic analysis is performed using two Canberra germanium detectors.
Due to environmental factors, the detectors could not be maintained in a calibrated status.
The manu-facturer has provided new equipment to correct this problem and the District has obtained satisfactory results with the detector used for liquid isotopic analysis.
Calibration and testing of the new detectors will be completed as soon as
- ~. ~
i f
I
' possible.
In the interim, isotopic analysis will be per-formed on diluted reactor coolant and containment atmosphere grab samples using existing detectors located in the plant chemistry laboratory.
(b)
Hydrogen levels are measured using the containment hydrogen analyzers.
i
'(c).
The gross dissolved gas analyzer (SL-24) has been tested and is operational.
The ion chromatograph used for boron and chloride analysis has been bench-tested and satisfactory re-sults were obtained.
Minor mechanical and electrical modi-fications are presently being made in preparation for in-stallation of the ion chromatograph.
Upon installation, the ion chromatograph will be functionally tested to verify on-line performance.
In the interim, diluted grab samples will be analyzed for boron and chloride concentrations using laboratory methods.
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 system (RWCUS)]
j
'to be placed in operation in order to use the sampling system.
Status Compliance with this design requirement is as detailed in the reference correspondence.
In accordance with Reference (5), the final SER, the District meets this requirement.
Criterion (4) i Pressurized reactor coolant samples are not required if the licen-see can quantify the amount of dissolved gases with unpressurized reactor coolant samples.
The measurement of either total dis-solved gases'or H2 gas in reactor coolant samples is considered adequate.
Measuring the 02 concentration is recommended, but is
.not mandatory.
Status The gross dissolved gas analyzer (SL-24) is operational.
Criterion (5)
The time for a chloride analysis to be performed is dependent upon two factors:- (a) if the plant's coolant water is seawater or brackish water and (b).if there is only a single barrier between primary containment systems and the cooling water.
Under both of
. the above conditions, the licensee shall provide for a chloride analysis within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the sample being taken.
For all other cases, the licenseo shall provide for the analysis to be completed within 4 days.
The chloride analysis does not have to be done on-site.
Status The capability for chloride analysis is discussed under Criterion (2).
Criterion (6)
The design basis for plant equipment for reactor coolant and con-tainment atmosphere sampling and analysis must assume that it is possible to obtain and analyze a sample without radiation ex-posures to any individual exceeding the criteria of GDC 19 (Appendix A, 10 CPR Part 50)
(i.e.,
5 rem whole body, 75 rem extremities).
[ Note that the design and operational review criterion was changed from the operational limits of 10 CFR Part 20 (NUREG-0578) to the GDC 19 criterion (October 20, 1979 letter from H.
R. Denton to all licensees.)]
Status Compliance with this design requirement is as detailed in the reference correspondence.
In accordance with Reference (5), the final SER, the District meets this requirement.
Criterion (7)
The analysis of primary coolant aanples for boron is required for PWRs.
(Note that Rev. 2 of Regulatory Guide 1.97 specifies the need for primary coolant boron analysis capability at BWR plants.)
Status l
l The capability for boron analysis is discussed under Criterion (2).
Criterion (8)
If in-line monitoring is used for any sampling and analytical cap-ability specified herein, the licensee shall provide backup l
sampling through grab samples and shall demonstrate the capability of analyzing the samples.
Established planning for analysis at offsite facilities is acceptable.
Equipment provided for backup l
sampling shall be capable of providing at least one sample per day l
for 7 days following onset of the accident and at least one sample per week until the accident condition no longer exists.
l
. Status The equipment required for reactor coolant and containment atmos-phere grab samples, both diluted and undiluted, has been tested and is operational.
In the event of failure of in-line monitoring instrumentation, analysis can be performed in-house in the Port Calhoun Station laboratory.
Please note that operability of the mechanical portion of the PASS is required in order to obtain these grab samples.
Criterion (9)
The licensee's radiological and chemical sample analysis capabi-lity shall include provisions to:
(a)
Identify and quantify the isotopes of the nuclide categories discussed above to levels corresponding to the source terms given in Regulatory Guide 1.3 or 1.4 and 1.7.
Where neces-sary and practicable, the ability to dilute samples to pro-vide capability for measurement and reduction of personnel exposure should be provided.
Sensitivity of onsite liquid sample analysis capability should be such as to permit measurement of nuclide concentration in the range from approximately 1 pCi/g to 10 Ci/g.
Status The gross gamma detectors used to measure gross activity and sample dilution are operational.
The status of the germanium detectore required for isotopic analysis is discussed under Criterion (2).
(b)
Restrict background levels of radiation in the radiological and chemical analysis facility from sources such that the sample analysis will provide result 3 with an acceptably small error (approximately a factor of 2).
This can be accomplished through the use of sufficient shielding around samples and outside sources and by the use of a ventilation system design which will control the presence of airborne radioactivity.
Status Compliance with this design requirement is as detailed in the reference correspondence.
In accordance with Reference (5), the final SER, the District meets this requirement.
Criterion (10)
Accuracy, range, and sensitivity shall be adequate to provide pertinent data to the operator in order to describe radiological and chemical status of the reactor coolant systems.
.... Status Instrument specifications for the operational portions of the PASS were provided in the SER.
Due to the interim methods being used for boron and chloride analysis, the required accuracy cannot be achieved using diluted samples.
Capability for ta%ing an undi-luted high pressure sample does exist as previously discussed in the SER.
The District has not been able to achieve proper calibration of 8
the pH cell used for on-line analysis.
We are working with the manufacturer to correct this problem.
pH measurements will be made on diluted grab samples in the interim.
The off-line germanium detectors which will be used for isotopic analysis of grab samples are capable of performing analysis equivalent to the on-line detectors.
The interim use of grab sample analysis will not affect the instrument specifications previously provided.
Criterion (11)
In the design of the post accident sampling and analysis capabi-lity, consideration 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 naterial in the RCS or containment, for appropriate disposal of the samples, and for flow restrictions to limit reactor 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 ac-cident.
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 close system.
(b)
The ventilation exhaust from the sampling station should be filtered with charcoal adsorbers and high-efficiency particulate air (HEPA) filters.
Status Compliance with this requirement is as detailed in the reference correspondence.
In accordance with Reference (5), the final SER, the District meets this requirement.
-.___________________________a