GO2-83-557, Forwards Procedures for post-accident Sample Analysis & Core Damage Evaluation,Per NUREG-0892 (Ser),Item II.B.3 & Section 9.3.2.4.GE Interim Dissolved Gas Analysis W/O Krypton Tracer Expected by End of June 1983
| ML17277A622 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 06/23/1983 |
| From: | Bouchey G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17277A623 | List:
|
| References | |
| RTR-NUREG-0892, RTR-NUREG-892, TASK-2.B.3, TASK-TM GO2-83-557, NUDOCS 8307050136 | |
| Download: ML17277A622 (4) | |
Text
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A('CaSRGN NBR:8307050136 DOC, DATE: 83/06/23 NOTARIZED:
NO FACIL:50 397 HPPSS Nuclear Pr oJecti Unit 2p Washington Public Powe AUTH BYNAME AUTHOR AFFILIATION
'OUCHEYiG,D, Nashington Public Power Supply System
'REC IP s NAME RECIPIENT AFFILIATION SCHIKENCERgA ~
Licensing Br anch 2
DOCKET 05000397
SUBJECT:
For wards procedures for post-accident sample analysis.
E core.
damage evaluationiper NUREG 0892 (SER)< Item II',3 L Section-
.9,3.?,0,GE interim dissolved gas analysis w/o krypton ti acer expected by end of June
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Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 June 23, 1983 G02-83-557 Docket No. 50-397 Director of Nuclear Reactor Regulation Attention:
Mr. A. Schwencer, Chief Licensing Branch No.
2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Schwencer:
Subject:
NUCLEAR PROJECT NO.
2 POST ACCIDENT SAMPLE ANALYSIS AND CORE DAMAGE EVALUATION PROCEDURES Attached are procedures for post accident sample analysis and core damage evaluation for WNP-2 fulfillingNUREG-0892 "Safety Evaluation Report related to the operation of WPPSS Nuclear Project No. 2",
March 1982, Section 9.3.2.4, Condition 6, "TMI Action Item II.B.3-Post Accident Sampling Capability" and related staff requirements discussed in Section 9.3.2.4.
The Core Damage procedure utilizes reactor water level measurements, radiation from fission gases in containment, hydrogen gas in contain-ment and isotopic analysis of reactor coolant and containment atmosphere to evaluate core damage.
The isotopic analysis is based on General Electric's NEDO-22215 "Procedure for the Determination of the Extent of Core Damage Under Accident Conditions", August 1982 by C.
C. Lin.
The attached procedure has been fully converted to WNP-2 and does not require the extra step of work through the standard General Electric reference plant.
The Post Accident Sampling and Analysis procedure contains procedures for:
Gamma Analysis Chlorides (ion chromotography)
Boron (ion chromotography)
Gas Sample Analysis (containment atmosphere)
Iodine and Particulate (containment atmosphere) pH of a Post Accident Sample (reactor coolant)
Dissolved Gas Analysis (later) 8307050136 830623
,'PDR ADOCK 05000397 E
0 Mr. A. Schwencer Page Two June 23, 1983 POST ACCIDENT SAMPLE ANALYSIS AND CORE DAMAGE EVALUATION PROCEDURES The Dissolved Gas Analysis is the one now being developed by General Electric for the BWR owners of General Electric sampling stations.
It will be included as procedure
- 12. 10.'8 when received.
An Interim Dissolved Gas Analysis without krypton tracer is being furnished initially by General Electric.
Receipt is expected by the end of June 1983.
We understand this procedure as used at Duane Arnold is acceptable to the NRC.
Should you have fur ther questions, please contact Mr. R.
M. Nelson,
- Manager, WNP-2 Licensing.
Very truly yours, G.
D. Bouchey
- Manager, Nuclear Safety and Regulatory Programs PLP/tmh Enclosure cc:
R Auluck -
NRC WS Chin
- BPA A
Toth NRC Site