W3P83-3918, Forwards Data Supporting Applicability of Selected Analytical Chemistry Procedure or on-line Instrument for post-accident Sampling Sys,In Response to Sser 2
| ML20082L724 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 11/29/1983 |
| From: | Cook K LOUISIANA POWER & LIGHT CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| W3P83-3918, NUDOCS 8312050567 | |
| Download: ML20082L724 (5) | |
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.o eO eGee P O W E R & L i G H T ! NEW OALEANS LOUISIANA 70174-000e G (504)308-2345
$iuS$ EYSSEM November 29, 1983 W3P83-3918 3-A1.01.04 3-D120 Director of Nuclear Reactor Regulation Attention:
Mr. G.W. Knighton, Chief Licensing Branch No. 3 D! vision of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
SUBJECT:
Waterford SES Unit 3 Docket No. 50-382 Poet Accident Chemistry Procedures and On-Line Instrumentation
Dear Sir:
In Supplement 2 to Waterford's SER the Staff required a submittal of data supporting the applicability of each selected analytical chemistry procedure or on-line instrument for the Post Accident Sampling System (PASS).
Enclosed please find the required response. This information has been discussed with your Mr. F. Witt (CEB) and supplemented to address his comments.
With this submittal LP&L has addressed all open items for the PASS. We request that your review of the PASS be included in the next Supplement to the Waterford 3 SER.
Should you have any questions or comments on this matter please contact Mike Meisner at (504) 363-8938.
Yours very truly, O
K.W. Cook Nuclear Support & Licensing Manager KWC/MJM/ch Enclosure cc: W.M. Stevenson, E.L. Blake, F. Witt (NRC), J. Wilson (NRC), G.L. Constable (NRC-Resident Inspector) h 9312050567 831129 PDR ADOCK 05000392 l
i
e SUITABILITY OF POST ACCIDENT CHEMISTRY PROCEDURES AND ON-LINE INSTRUMENTATION (1) Boron
- Boron analysis will be performed by plasma spectroscopy on a 1000:1 diluted sample. A Beckman spectraspan V will be used for this analysis.
The NRC study by Exxon (Reference 1) concluded that this method has suitable sensitivity with diluted samples and can be done in the required time frame. Testing with the standard matrix did not show any interference problems.
(2) Chloride
- Chloride analysis will be performed offsite by Oak Ridge National Laboratory. They will use an Ion Chromatograph.
Reference 1 concluded, and Reference 2 demonstrated the suitability of this method. An undiluted degassed RCS or SIS sump sample will be collected and shipped to Oak Ridge for analysis within the required 4 day time frame.
(3) Dissolved
- Dissolved oxygen will be performed using an in-line Oxygen oxygen probe and remote analyzer and recorder. The in-strumentation is a Yellow Springs Instrument Corpany tbdel 56.
Testing performed by NUS (Reference 2) demon-strated that this analyzer and probe can be used to obtain analyses in the range of 0.1 to 20 ppm with an accuracy of 110%. The NRC confirmed (Reference 3) that dissolved oxygen is not required by NUREG 0737 because it can be inferred from the hydrogen concentration.
Backup grab sample capability for dissolved oxygen is not provided.
(4) RCS Hydrogen-Hydrogen analysis on RCS samples will be performed on-line using the gaseous portion stripped from the RCS stream. A Hays-Republic Model 643E Thermoconductivity analyzer will be used. Tests confirm (Reference 4) that this equipment is suitable for accident condition radiation fields. As a backup to the on-line deter-mination, a grab sample will be analyzed in the lab on l
a Carle Gas Chromatograph. Reference 5 reported that Babcock and Wilcox have verified suitability of a gas chromatograph on TMI samples.
(5)
Containment - Hydrogen analysis on the containment atmosphere will be Atmosphere performed on-line using a Delphi Thermoconductivity Hydrogen analyzer. This is the same instrument as required by Reg. Guide 1.97.
Radiation effects testing on the Delphi was conducted by CE as reported in Reference 6.
A grab sample can be obtained and analyzed on a Carle Gas Chromatograph as a backup.
i Continued...
(6) pj{
- The pH will be determined on-line with a Hays-Republic Model A-62604 analyzer and probe. The probe is located such that it can be flushed and removed for repair or replacement. Radiation effects testing (Reference 7) on similar pH probes indicates that pH measurement will not be affected at the projected radiation levels.
(7) Radionuclides-Radionuclide determinations on RCS, SIS-sump, and containment atmosphere grab samples will be performed using an intrinsic gamma ray detector in conjunction with a ND-6620 computer. RCS and SIS-sump grab samples will be obcained at a 1000:1 dilution. Undiluted contain-ment atmosphere grab samples will be obtained for subsequent dilution in the lab prior to counting.
(3) Instrument - See Table-1 attached.
Ranges &
Accuracy i
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TABLE 1 POST ACCIDENT CHEMISTRY ON-LINE INSTRUMENTS DETERMINATION INSTRUMENT RANGE ACCURACY COMMENTS Boron Beckman Spectrospan V 100-100,000* ppm
< 1000!10%
- Instrument Range
> 1000 5%
based upon.1000:1 dilution Dissolved Yellow Springs Instruments
.10-20 ppm
!10%
0xygen Model 56 pH Hays Republic Model A-62604 1-13 pH units
.3pH units RCS Hydrogen a) on-line a) Hays Republic Model 643E 0-100%
1%
Thermoconductivity Analyzer b) Grab Sample b) Carle Gas Chromatograph 0-100%
5%
Cont. Hydrogen Delphi Thermoconductivity 0-10%
Analyzer Radionuclides PGT Intrinsic Detector 1 uci/cc-within factor with ND 6620 computer 10 Ci/cc of 2 across entire range l
REFERENCES 1.
" Evaluation of GE and SEC Chemical Procedures for Postaccident Analysis of Reactor Coolant Samples", Exxon Nuclear Idaho, Inc.
Report for U.S. Nuclear Regulatory Commission, Nov.1981 2.
" Generic Response to NUREG-0737, II.B.3., Evaluation Criteria Guidelines for PASS Owners Group", NUS Report R-31-9-29, Sep. 1982 3.
" Post Accident Sampling System", Telecon between F.J. Witt (U.S. Nuclear Regulatory Commission) and M.J. Meisner/D.E. Adams (LP&L), July 25, 1983 4.
"SWRI Project No. 11-5453-013, Final Report:
Irradiation of Instrumentation", Letter to F.M. Riedel (Milton Roy Company) from D.G. Cadena (Southwest Research Institute), Nov. 19, 1979 5.
" Post Accident Sampling Analytical Procedures", Letter to L.L. Kintner (U.S. Nuclear Regulatory Commission) from H. Tauber (Detroit Edison Co.), NRC Docket No. 50-341, July 7, 1982 6.
" Emergency Evaluation and Functional Testing for CE PASS Components and Instrumentatica", Combustion Engineering Report CEN-229(L)-NP, Nov. 1982 7.
"An Evaluation of On-Line Boron Analyzers", Nuclear Safety Analysis Center Report NSAC-46, April 1982