ML20203C904
| ML20203C904 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 04/17/1986 |
| From: | Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | Noonan V Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM SBN-1007, NUDOCS 8604210261 | |
| Download: ML20203C904 (7) | |
Text
r SEABROOK STATION Engineering Office ONdbM April 17, 1986 New Hampshire Yankee Division SBN-1007 T. F.
B7.1.2 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) NUREG-0896, Supplement No. 3, " Safety Evaluation Report Related to the Operation of Seabrook Station Units 1 and 2", dated July, 1985 (c)
" Radiological Analysis of the Seabrook Station Unit 1 Post-Accident Sampling and Analysis Capability",
YAEC Safety-Related Calculation SBC-135, Revision 0, dated March 3, 1986
Subject:
NUREC-0737, Task II.B.3, " Post-Accident Sampling System",
Criterion (6) - Shielding Analysis
Dear Sir:
In Subsection 9.3.4.2, " Evaluation - II.B.3 Post-Accident Sampling System" of Reference (b), the discussion for Criterion (6) states:
"The applicant will perform a shielding analysis to ensure that operator radiation exposure from reactor coolant / containment atmosphere sampling and analysis is within the acceptable limits of 5 rem whole body and 75 rem extremities".
Purs uant to this commitment, an analysis was performed for Seabrook
[ Reference (c)] which concludes that doses to any individual obtaining and analyzing a sample following a design basis accident are within the limits of General Design Criterion 19 of Appendix A to 10CFR50.
A summary, including results, of the analysis is provided in Attach-ment 1.
Also enclosed herewith as Attachment 2, is a revision to PS AR Section 1.9 concerning Task II.B.3 which will be incorporated into the FSAR via a future amendment.
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Seabrook Station Construction Field Office. P.O. Box 700 + Seabrook, NH 03874
F United States Rrgulatory Commission Attention:
Mr. Vincent S. Noonan Page 2 We trust the informat on provided herewith is acceptable and request the resolution of this issue be reflected in the upcoming supplement to Scabrook's SER.
Very truly yours,
', 4 L-s /
J John DeVincentis, Director Engineering and Licensing Attachment cc: -. Atomic Safety and Licensing Board Service List
Administrative Judge Helen Hoyt, Chairperson Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Administrative Judge Sheldon J. Wolfe, Chairman Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Dr. Emmeth A. Luebke Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Dr. Jerry Harbour Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission 4
Washington, D.C. 20555 t
O
Dicnn Curran, E: quire Csivin A. Cann:g Normon & Weiss City Manager 2001 S. Street, N.W.
City Hall Suite 430 126 Daniel Stredt Washington, D.C.
20009 Portsmouth, NH 03801 Sherwin E. Turk, Esq.
Stephen E. Norrill, Esquire Office of the Executive Legal Director Attorney General U.S. Nuclear Regulatory Commission George Dana Bisbee, Esquire Tenth Floor Assistant Attorney General Washington, DC 20555 Office of the Attorney General 25 Capitol Street Robert A. Backus Esquire concord, NH 03301-4397 116 Lowell Street P.O. Box 516 Nr. J. P. Nadevv Nanchester, NN 03105 Selectmen's Ottace 10 Central Road Philip Ahrens, Esquire Rye, NH 03870 Assistant Attorney General Department of The Attorney General Mr. Angle Nachiros Statehouse Station #6 Chairman of the Board of Selectmen kugusta NE 04333 Town of NeWbury Newbury, MA 01950 Mrs. Sandra Cavutis Chairman, Board of Selectmen Nr. William 3. Lord 1
RFD 1 - Box 1154 Board of Selectmen Kannsington, NH 03827 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, MN 03301 Boston, MA 02108 (ATTN: Herb Boynton)
Senator Gordon J. Humphrey N. Joseph Flynn, Esquire U.S. Senate Office of General Counsel Washington, DC 20510 Federal Emergency Nanagement Agency g (ATTW: Tom Burack) 500 C Street, SW f
Washington, DC 20472 Richard A. Hampe, Esq.
l Hampe and McNicholas Paul McEachern, Esquire j
35 Pleasant Street Matthew T. Brock, Esquire Concord, NH 03301 Shaines & McEachern 25 Naplewood Avenue i
Donald E. Chick P.O. Box 360 I
Town Manager Portsmouth, NH 03801 Town of Exeter 10 Front Street Gary W. Holmes, Esq.
Exeter, MN 03833 Holmes & Ells 47 Winnacunnet Road Brentwood Board of Selectmen Hampton, NH 03841
)
RFD Dalton Road i
Brentwood, NH 03833 Nr. Ed Thomas i
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 3
P.O. Box 710 North Hampton, NH 03862
SBN-1007 ATTACHMENT 1 DESIGN DOSE
SUMMARY
OF RCS AND CONTAINMENT AIR SAMPLING The steps for post-accident RCS sampling are as follows:
An operator collects two 1/2 cc syringes containing RCS gas sam-ples and two 10 cc syringes containing RCS liquid samples f rom the post-accident sample panel and transports them to the chemistry laboratory.
In the laboratory, the liquid samples are discharged to beakers behind the shield wall under the fume hood.
Samples are later prepared from these and analyzed.
One gas syringe is discharged to an aliquot for the isotopic analysis; the other is discharged into the gas chromatograph for analysis.
The steps for post-accident containment atmosphere sampling are as follows:
An operator collects one 40 cc containment atmosphere sample and transports the sample to the chemistry laboratory where a small quantity is drawn of f (via syringe) and injected into the gas chromatograph. A small quantity is similarly drawn off and in-jected into an aliquot for isotopic analysis.
All samples are transported, unshielded in containers such that samples are at least 1/2 foot from the operator's whole body and ext <emities.
Operations have been timed, potential sources inventoried, transit paths analyzed, dose-limiting source-shield-detector geometries estab-lished, dose rates calculated, and the dose to each operator calculated.
It should be noted that no one single operator / technician will perform enough operations that will allow him to exceed the allowable dose limits.
The doses associated with each operation are summarized below:
Dose to Dose to Operation Whole Body Extremities Obtain RCS Samples
.96 r em 7.2 rem Analyze RCS Gas Sample
.48 5.1 Analyze RCS Liquid Sample 1.5 6.6 Align Containment Air Sampler 1.3 1.3 Obtain Containment Air Sample 1.8 6.3 Analyze Containment Air Sample 1.1 17.
_-~
r ATTACHMENT 2 SBN-1007 SB 1 & 2 Amsndment 56 FSAR November 1985 I-,I v.
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 euxiliary 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.adiological 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 tern). 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 Res ponse :
Sec FSAR Section 9.3.2.
In addition, information has been provided to the NRC in the following letters:
SBN-514 (dated May 31, 1983),
h p),* h l
SBN-648 (dated April 16, 1984), and
_ y a
SBN-741 (dated December 18, 1984).
]g3d. A 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 systema to control or mitigste accidents in which
~
the core is severely damaged. They must then implement the training program.
Response
See FSAR Sections 13.2.1 and 13.2.2.
54.
1.9-11
(
ATTACHMENT 2 SBN-1007 Insert " A" on pg.-1.9-11 l
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.
i 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 Me*hodology.
9:W-1007 (dated April 17, 1986), submitted the results of the Shielding Analysis.
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