ML19345F444
| ML19345F444 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/19/1981 |
| From: | Snyder B Office of Nuclear Reactor Regulation |
| To: | Arnold R METROPOLITAN EDISON CO. |
| Shared Package | |
| ML19345F445 | List: |
| References | |
| NUDOCS 8102170501 | |
| Download: ML19345F444 (2) | |
Text
.
JAN 1 9 sc1 D
Docket No. 50-320 i
e _.msi-m Y""E Mr. R. C. Arnold O
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Senior Vice President Metropolitan Edison Cogany
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100 Interpace Parkway Parsippany, New Jersey 07054
Dear Mr. Arnold:
We have cogleted our review of the TMI-2 reactor coolant water chemistry program with respect to ongen suppression including the MAKSD1A-CHEMIST comuter analysis and Orbisphere oxygen detector tests results. Although the MAKSIMA-CHDtIST analysis presented by Met Ed/GPU is theoretically correct, it cannot be concluded that hydrogen levels of greater than 5 std cc/kg will control the dissolved oxygen to 0.1 ppm due to presence of im-purities such as dissolved and collodial iron which can co@ete with radio-lytic recocbination of hydrogen and oxygen. As a result the oxygen may rise to a concentration level cogarable with that of the igurities. However, maintenance of a residual hydrazine concentration in the reactor coolant (which is currently the practice) will control the oxygen level to 0.1 ppm.
We have reviewed the Orbisphere test results and conclude that use of a properly calibrated Orbisphere will provide sensitivity down to the 0.1 ppm oxygen level and is acceptable.
We have prepared the enclosedsurveillance requirements for axygen and pH levels in the reactor coolant which will be incorporated into.the Recovery Operations Plan. These requirements have been discussed with and agreed to by members of your staff. We have also prepared and enclosed a revision to the Technical Specification bases which contains a sumary of our reasons for these requirements.
i Based on our review of your reactor coolant chemistry control program, oxygen sampling capability and incorporation of the surveillance requirements into the Recovery Operations Plan, we conclude that the potential for chloride stress and general stress corrosior: will be minimized and that you have satis-i factorily addressed our concerns.
81021'70501 g
A copy of the related Safety Evaluation is enclosed.
Sincerely.
l h
i Bernard J. Snyder, Program Director Three Mile Island Program Office l
Office of Nuclear Reactor Regulation
Enclosures:
1.
Safety Evaluation 2.
Recovery Operations Plan, page 4.4-1 3.
Technical Specification Bases, page B 3/4 4-1 Distribution:
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- 1979 289 369