ML20084C581
| ML20084C581 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 04/16/1984 |
| From: | Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE, YANKEE ATOMIC ELECTRIC CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, TASK-2.B.3, TASK-TM SBN-648, NUDOCS 8404300113 | |
| Download: ML20084C581 (2) | |
Text
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.2 Pub 4c Service of New Hampshke April 16, 1984 Director of Nuclear Reactor Regulation Attention:
Mr. George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing United States Nuclear Regulatory Commission Washington, D. C.
20555
References:
(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 Subj ect:
NUREG-0737 ITEM II.B.3 " Post-Accident Sampling Capability"
Dear Mr. Knighton:
Public Service Company of New Hampshire (PSNH) recently initiated a series of telephone conversations with Mr. Paul Wu and Mr. Vic Nerses of your staff for the purpose of obtaining hTC clarifications on post-accident sampling requirements stated in NUREG-0737, Item II.B.3.'
Specifically, we
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were seeking further NRC guidance on Criterion (4) with regards to dissolved hydrogen and oxygen monitoring of the reactor coolant and on Criterion (5) with regards to pH measurement of the reactor coolant. The purpose of this letter is to document the clarifications PSNH received from your staff and to describe our methodology for compliance.
NRC Criterion (4) Clarification The determination of dissolved oxygen can be satisfied by analyzing a post-accident gas sample from the reactor coolant system for dissolved hydrogen. If the reactor coolant dissolved hydrogen concentration is greater than 10 cc/kg, the NRC considers the dissolved oxygen level to be less than 100 ppb.
If the post-accident dissolved hydrogen level is less than 10 cc/kg, the NRC will require PSNH to provide justification that no damage to plant systems has occurred prior to plant startup, but considers the analysis requirement for oxygen satisfied.
PSNH Response The amount of, dissolved gases in the reactor coolant will be determined by extracting a gaseous sample from the post-accident sampling panel using a-shielded syringe if necessary. This sample will be analyzed for hydrogen and gamma spectrum only.
8 8404300113 840416 I M DR ADOCK 05000443 N
PDR 1000 Elm St., P.O. Box 330, Manchester, NH 03105 Tvephone (603) 669-4000 TWX 71O2207595
P cuc trayect couPANY or New Haupswear paar 2 3
NRC Criterion (5) Clarification The licensee shall have developed procedures to obtain pH and chloride analysis data on the undiluted sample after thirty days decay. The sample can be analyzed on-site or shipped off-site for analysis. This analysis for pH on the undiluted sample satisfies pH requirements, and there is no need to install in-line instrumentation for pH measurement.
PSNH Response The post-accident sampling system (PASS) will provide for the capability of taking a single undiluted sample consistent with ALARA principles. This undiluted sample will be retained for analysis within thirty days. Procedures for drawing the undiluted sample and for the analysis of the undiluted sample for chloride and pH are under development and will be available six months prior to fuel load. A dose assessment of the undiluted sample has been per-formed and, using the assumptions employed in the design basis of the PASS panel, pH and chloride analysis can be performed on the undiluted sample con-sistent with the criteria in GDC 19.
s Please contact my staff if your understanding of the conversations differs from ours, or if you require further information concerning our responses.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY
/O John DeVincentis Project Manager o
JD/SDF:dh cc: Atomic Safety and Licensing Board Service List
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