ML20141H155
| ML20141H155 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 04/22/1986 |
| From: | Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | Noonan V Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-0896, RTR-NUREG-737, RTR-NUREG-896, TASK-2.B.3, TASK-TM SBN-1008, NUDOCS 8604240122 | |
| Download: ML20141H155 (6) | |
Text
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SEABROOK STATION Engineering Office I
b April 22, 1986 SBN-1008 gmgmp T.F.
B7.1.2 NEW HAMPSHIRE YANKEE DIVISION United States Nuclear Regulatory Commission Washington, DC 20555 Attention:
Mr. Vincent S. Noonan, Project Director PWR Project Directorate No. 5
References:
(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) PSNH Letter, dated May 31, 1983, "Open Item Response (SER Section 9.3.4.2; Chemical Engineering Branch),"
J. DeVincentis to G. W. Knighton (c)
NUREG-0896, Supplement No. 3, " Safety Evaluation Report Related to the Operation of Seabrook Station Units 1 and 2", July 1985 Subj ect :
NUREG-0737, Task II.B.3, " Post-Accident Sampling System,"
Criterion (10) - Accuracy, Range and Sensitivity
Dear Sir:
In subsection 9.3.4.2, " Evaluation - II.B.3 Post-accident Sampling" of Reference (c) the conclusion for Criterion (10) states:
"(a) develop more sensitive analysis methods for chemical and radiological analyses; (b) provide information on ranges and accuracies for these analyses demonstrating applicability of procedures and instrumentation in the post-accident water chemistry and radiation environment; and (c) retrain operators on a semi-annual basis."
Concerning Item (a) Seabrook selected methods and instruments that were successfully used in a similar environment and performed tests utilizing the standard test matrix recommended by the Staf f and quoted in Reference (b).
Seabrook employs the methodologies deemed most appropriate by Exxon Nuclear Idaho Company, Inc. in their " Evaluation of GE and SEC Chemical Procedures for Post Accident Analysis of Reactor Coolant Samples" done for the Nuclear Regulatory Commission in November 1981.
These methodolo-gies include:
o Fluoroborate Selective Ion Electrode for Boron o
Ion Chromatography for Chloride o
Gas Chromatography for Dissolved liydrogen o
pH Probe for pli
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8604240122 860422 PDR ADOCK 05000443 l
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PDR Seabrook Station Construction Field Office. P.O. Box 700 Seabrook, NH O3874
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United States Nuclear Regulatory Commission Attention:
Mr. Vincent S. Noonan Page 2 Seabrook developed the applicable PASS Procedures which were sub-mitted to the Staff on July 25, 1985 as Chapter 6 of the Emergency Response Manual.
The revisions to these procedures are sent under controlled distribution to the Staff. Using these procedures and af ter calibration of the equipment, the analytical methods were tested using the standard test matrix. This testing established the appropriateness of these analytical methods.
It should be noted that this testing was redundant to the testing documented by Exxon.
A discussion of the information required by Item (b) of Criterion (10) is presented in Attachment 1.
Regarding Item (c) Seabrook operators are trained semi-annually on the chemistry procedures. The last training in this area took place in January, 1986.
At tachme nt 2 is FSAR Page 1.9-11 marked to show compliance with the requirements of NUREG-0737, " Clarification of TMI Action Plan Requirements".
The changes will be incorporated in the FSAR via a future amendment.
Also enclosed as Attachment 2 is a revised excerpt of FSAR Section 1.9 showing compliance with the requirements of NUREG-0737, Clarification of TMI Action Plan Requirements." These changes will be incorporated into the FSAR via a future amendment.
It should be noted that final testing of the integrated system involving both the PASS panel and the analytical methods together will be done once the system is completed.
This acceptance testing will be per-formed to show the accuracy of the diluted sample obtained f rom the PASS panel in comparison with normal grab samples f rom the reactor coolant system for both chemical and radiochemical parameters.
The system will be operational prior to exceeding 5% power as stated in the SER.
Very truly yours, y li John DeVincentis, Director Engineering and Licensing Attachment cc:
Atomic Safety and Licensing Board Service List
Dicn3 Curran, Esquire Calvin A. Ccanor Harmon & Weiss City Manager 2001 S. Street, N.W.
City Hall Suite 430 126 Daniel Street Washington, D.C.
20009 Portsmouth, NH 03801 A
Shervin E. Turk Esgi Stephen E. Morrill, Esquire Office of the Executhe Legal Director Attorney Ceneral U.S. Nuclear Regulato'ry Coassission George Dana Bisbee, Esquire Tenth Floor Assistant Attorney General Washington, DC 20555 office of the Attorney Ceneral 25 Capitol Street Robert A. Backus Esquire Concord, NH 03301-6397 116 Lowell Street P.O. Box 516 Nr. J. P. Nadeau Manchester, NH 03105 Selectmen's Office 10 Central Road Philip Ahrens, Esquire Rye, NH 03870 Assistant Atto mey General Department of The Attorney Genersi Mr. Angle Machiros Statehouse Station M i
Chairman of the Board of Selectmen hugusta, NE 04333 Town of Newbury Newbury, MA 01950 a
Mrs. Sandra Cavutis i
Mr. William S. Lord chaiman, Board of Selectmen RFD 1 - Box 1154 Board of Selectmen Kennsington, NH 03027 Town Hall - Friend Street Amesbury, MA 01913 Carol S. Sneider Esquire Assistant Attorney General Senator Gordon J. Humphrey Department of the Attorney General 1 Pillsbury Street One Ashburton Place, 19th Floor Concord, NH 03301 Boston, MA 02108 (ATTN: Herb Boynton)
Senator Cordon J. Humphrey H. Jos'sph Flynn, Esquire U.S. Senate Office of General Counsel Washington, DC 20510 Federal Energency Management Agencyg (ATTN: Tom Burack) 500 C Street, SW Washington ( DC 20472 Richard A. Hampe, Esq.
Hampe and McNicholas Paul McEachern Esquire 35 Pleasant Street Matthew T. Brock Esquire Concord, NH 03301 Shaines & NcRachern 25 Maplewood Avenue Donald E. Chick P.O. Box 360 Town Manager Portsmouth, NH 03801 Town of Exeter 10 Front Street Cary W. Holmes, Esq.
Exeter, NH 03833 Holmes & Ells 47 Winnacunnet Road Brentwood Board of Selectmen Hampton, NH 03841 RFD Dalton Road Brentwood, NH 03833 Mr. Ed Thomas FEMA Region I Peter J. Mathews, Mayor 442 John W. McCormack PO & Courthouse City Hall Boston, MA 02109 Newburyport MA 01950 Stanley W. Knowles, Chairman Board of Selectmen P.O. Box 710 North Hampton, NH 03862
i ATTACHMENT 1 SBN-1008 DISCUSSION OF SEABROOK STATION'S POST-ACCIDENT SAMPLING METHODS INTRODUCTION:
Data is presented justifying the use of methods developed for analy-sis of boron, chloride and hydrogen concentrations in post-accident samples.
The methods were developed to be quick and reliable for use on highly radioactive samples.
The analyses are performed on grab samples.
Sample volumes have been minimized in order to minimize radiation exposure to personnel.
DISCUSSION:
Boron by Specific Ion Electrode Boron concentration in liquid samples is analyzed as fluoroborate ion by a fluoroborate-specific ion electrode in conjuaction with a double-junction reference electrode.
This procedure was developed for the range of 1 ppm t o 10 ppm B; higher concentrations may be determined by dilution.
Calibration curves were also prepared with boron standards in a post-accident reactor coolant matrix. The matrix tested consisted of approximately as Ba(NO )2, 5 ppm La+++
40 ppm I as KI, 250 ppm Cs+ as CsNO 10 ppm Ba*+
3, 3
as La(NO )3 and 2 ppm Li+ as LiOR, diluted 1000:1.
The matrix was determined 3
to have no affect on the linearity of the calibration curve.
Chlorides by Ion Chromatography Chlorides may be determined in liquid samples using the Dionex System 2020. The procedure is applicable in the range of sub ppb Cl to 100 ppb chlorides, or higher when properly calibrated. The method requires prep-eration of very low level chloride standards for calibration purposes.
The reactor coolant test matrix previously described does not interfere with accurate determination of chlorides by ion chromatography.
Hydrogen Gas by Cas Chrom;tography 5
Percent hydrogen in <aseous samples is analyzed by gas chromatography utilizing a Ferkin-Elmer $1gma 3B Gas Chromatography.
The method is applicable in the range of 1% to pure hydrogen.
High concentrations are determined by varying sample injection volumes.
is most accurately determined in the It has been determined that H2 presence of He by calibration of the gas ghromatograph with standards containing equal amounts of both gases di, solved in argon. Good peak separation is obtained with good reproducibility.
.The column is heated to 75'C for percent hydrogen determination and then baked at 125*C to prevent xenon pt,isoning.
ATTACHMENT 2 SBN-1008 SB 1 & 2 Amendment 56 FSAR Nove:ber 1985
(
products.
If the review indicates that personnel could not promptly and safely obtain the samples, additional design features or shielding should be provided, to meet the criteria.
A design and operational review of the radiological spectrum analysis facilities shall be performed to determine the capability to promptly quantify (in less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) certain radionuclides that are indicators of the degree of core damage. Such radionuclides are noble gases (which indicate cladding failure), iodines and cesiums (which indicate high fuel temperatures), and nonvolatile isotopes (which indicate fuel melting). The initial reactor coolant spectrum should correspond to a Regulatory Guide 1.3 or 1.4 release. The review should also consider the effects of direct radiation from piping and components in the auxiliary building and possible contamination and direct radiation from airborne effluents. If the review indicates that the analyses required cannot be performed in a prompt manner with existing equipment, then design modifications or equipment procurement shall be undertaken to meet the criteria.
In addition to the radiological analyses, certain chemical analyses are necessary for monitoring reactor conditions. Procedures shall be provided to perform boron and chloride chemical analyses, assuming a highly radioactive initial sample (Regulatory Guide 1.3 or 1.4 source teru). Both analyses shall be capable of being completed promptly (i.e., the boron sample analysis within an hour and the chloride sample analysis within a shift).
i
Response
See FSAR Section 9.3.2.
In addition, information has been provided to the NRC in the following letters:
[SBN-514(datedMay 31, 1983),
__ yMm u),*h SBN-648 (dated April 16,1984), and E
i a
SBN-741 (dated December 18, 1984).
Inuk A E
Task II.B.4 Training for Mitigating Core Damage (NUREC-0737)
Position:
Licensees are required to develop a training program to teach the use of installed equipment and systems to control or mitigate accidents in which the core is severely damaged. They must then implement the training program.
Response
3ee FSAR Sections 13.2.1 and 13.2.2.
Sc.
1.9-11
ATTACHMENT 2 SBN-1008 Insert "A" on pg. 1.9-11 SBN-514 (dated May 31, 1983), provided responses to all 11 Criteria.
SBN-648 (dated April 16, 1984), provided clarification to Criteria 4 and 5.
SBN-741 (dated December 18, 1984), reflected the removal of the Pressurizer Relief Tank sample from the PASS design.
SBN-964 (dated March 6, 1986), submitted the Core Damage Assessment Methodology.
SBN-1007 (dated April 17, 1986), submitted the results of the Shielding Analysis.
SBN-1008 (dated April 22, 1986), submitted inf ormation on the accuracy, range, and sensitivity of PASS inst rumentation and analytical procedures.
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