ML19329A388
| ML19329A388 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/17/1977 |
| From: | Grimes B Office of Nuclear Reactor Regulation |
| To: | Goller K Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19329A389 | List: |
| References | |
| NUDOCS 8001030962 | |
| Download: ML19329A388 (2) | |
Text
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MEMORANDUM FOR:
K. Goller, Assistant Director for Operating Reactors. D0R 1
l FROM:
B. Grimes, Chief, Environmental Evaluation Branch, 00R i
SUBJECT:
OCONEE - TECHNICAL SPECIFICATION NENDMENT TO CONTROL SECONDARY-SIDE RADI0 ACTIVITY j
PLANT NAME: Oconee Nuclear Station, Units Nos.1, 2 and 3 DOCKET NOS.: 50-269, -270. -287 RESPONSIBLE BRANCH: ORB #1 PROJECT MANAGER:
D. Neighbors REVIEW STATUS: EEB - Coglete In response to EEB reconnendations (July 7,1977 letter from B. Grimes to K. Goller), an NRC letter dated August 4,1977 was sent to Duke Power Company requesting the licensee to propose revisions to the Oconee Techni-cal Specifications. We have completed our review of this matter and have prepared a safety evaluation which is enclosed.
Our recomended revisions censisted of:
1) inclusion of an operational requirement on the installed tur-bine building sump monitor with an alam in the control room.
- 2) addition of a composite water sampler at the outfall of the
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oil collection basin with weekly gama spectra analysis and i
quarterly Sr-89 and Sr-90 analysis, and
- 3) addition of a requirement for two independent checks on valve alignment for discharge of radioactive spent resin from the secondary water clean-up system to the receiving tanks to pre-vent an inadvertent release of highly contaminated resins to the waste water collection basin following steam generator leaks.
We concluded that these additional monitoring and administrative controls were required at the Oconee facility to keep radioactive releases "as low as reasonebly achievable" in accordance with Appendix I to 10 CFR Part 50.
Additionalif, these revisions were determined to be necessary in maintain-ing adequate control of secondary-side radioactivity, which was the subject of DDR Inforsation Memorandum No. 5.
Duke Power Company replied by letter 7n p3 cop 7 j,. J """^"'X ostaet: J. S. Bl::d M;
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dated September 27,1977. and amended by letter dated October 14,1977, 1'
stating their intention to conduct the above action on a voluntary basis j
but did not consider a revision to the Technical Specifications necessary.
Duke also took exception to the recomendation of routine analysis of the j-oil collection basin outfall for Sr-89 and Sr-90. They considered this analysis necessary only in the event of an inadvertent release. We have 1-ev&1uated Duke's letters of comitment and discussed the istue with Region II (A. Kowelczuk, Oconee radwaste inspector, and A. Gibson, Section Chief.
J FFMS Branch). We have determined that the monthly strontium ar.alysis is needed and that Technical Specifications on these items are necessary to assure that I&E has the tools to enforce the objectives of the recomended revisions..
In addition, we have evaluated the Duke Power Company letters of December 2 1976 and August 4, t t77 which address the Oconee procedure for controlling very low level radue 'N resins from'the secondary water clean-up system.
The Duke' procedure
' ts of discharge of these resins to the waste water.
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collection basins.
dure specifies a maximum inventory of radio-activitt for the bau w 2it the consequences of any potential release of radioactivity from tus pathway 1.6 a fraction of the Appendix I design objective doses. While the Oconee mettod of control of very low level radio-active spent resins is acceptable, a restision to the Teclinical Specifications incorporating the Oconee procedures and maximum radioactivity limits for the discharge of the msins is necessary. Also, a surveillance requirement for an annual sample and radioactive analysis of the waste water basin bottoms f
is needed to verify the total quantity cf radioactivity in the basins. These revisions to the Oconee Technical Specifications will assure adequate oro-cessing of radioactive spent resins and adequate control of radioactivity in the waste, water collection basins.
As requested by the ORPM, D. Neighbors, a Safety Evaluation is enclosed to support a license' amendment incorporating the recomended revisions in the Oconee Technical Specifications.
The appropriate wording and location of the revisions will be worked out be-tween Duke Power and the NRC'(D. Neighbors ORB #1 and J. S. Bland, EEB).
Additional discussion on the technical basis of the Technical Specification
,~
Ntvision'is also provided in the Safety Evaluation, ogr.at sisned by Brian K. Grimes Brian K. Grimes, Chief Environmental Evaluation Branch
Enclosure:
As stated DISTRIBUTION BGrimes cc:
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