ML20214E216
| ML20214E216 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 05/14/1987 |
| From: | Andognini G SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Miraglia F Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20214E217 | List: |
| References | |
| GCA-87-030, GCA-87-30, NUDOCS 8705220008 | |
| Download: ML20214E216 (2) | |
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$SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O P. o. Box 15830, Sacramento CA 95852-1830,1916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA GCA 87-030 AIAY I 41987 Director of-Nuclear Reactor Regulation Attn:
Frank J. Miraglia Director PWR-B Division U S Nuclear Regulatory Commission Washington, DC 20555 Docket No. 50-312 Rancho Seco Nuclear Generating Station License No. DPR-54 PROPOSED AMENDMENT NO. 111, REV. 1
Dear Mr. Miraglia:
Proposed Amendment No. 111, submitted to the NRC on February 28, 1986, revised Table 3.6-1, Safety Features Containment Isolation Valves incorporating 16 additional valves and increasing the maximum closure time of certain of the containment isolation valves to 25 seconds.
In a subsequent telephone conversation (S. Miner, NRC to R. Colombo, SMUD), the NRC requested that SMUD reevaluate the effect of containment parging coincident with a LOCA using TID source terms instead of reactor coolant inventory terms.
The District has reviewed the licensing criteria for containment purging coincident with a LOCA and notes the following in Branch Technical Position CSB 6-4, Section B.5.a:
The source terms used in the radiological calculations should be based on a calculation under the terms of (10 CFR 50), Appendix K, to determine the extent of fuel failure and the concomitant release of fission products, and the fission product activity in the primary coolant.
A pre-existing iodine spike should be considered in determining primary coolant activity.
District interpretation of this BTP passage and its reference to 10 CFR 50, Appendix K indicates that the modeling of the release of radioactivity to the containment environment need not be instantaneous, as would be assumed with the use of TID source terms during the first feu minutes of a LOCA.
Therefore, it is concluded that the release of radioactivity to the containment environment should be time-dependent, not instantaneous.
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.0 8705220008 870514 PDR ADOCK 05000312 1,( i p
PDR DISTRICT HEADQUARTERS O 6201 S Street, Sacramento CA 95817-1899
MA 141987 O
F. J. Miraglia~
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The attached Proposed. Amendment'No. 111,ORevision.1 submits'_a-
, revised Safety Analysis (Attachment II) to'further clarify the
- District's--position of using reactor coolant inventory source 4
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-terms to determine the"25 second maximum closure ~ times-of the
. select containment isolation valves. -Additionally, Attachmenti
}~
III, the "No Significant. Hazards"' consideration is, revised to
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better comply.with.10 CFR 50.92, as clarified by Generic Letter-i
~86-03.-
The remainder'of Proposed Amendment'No. 111, Revision 1; L
submitted herewith, is unchanged from the original submittal.-
except for.the deletions of_ Attachment III-a_ndlIV, which are:
l
- supplanted by-the revised Safety Analysis, Land reformatting of
-Table 3.6-1 for improved understanding of valve positioning (Attachment I).
- Pursuant to '10 CFR 50.91(b) (1),- the Radihlogical ' Health _ Branch ~ of the California State Department of Health' Services-has been informed of this proposed amendment by mailed copy of this-l submittal..
The District has_ determined that~no-license' fees are required with this revision since a check for $150.00 was~sent to the Commission with the initial submittal of Proposed Amendment No.
138.
Should _ you -require any further information: concerning Proposed I-Amendment No.' 111, Revision 1, please contact Mr. Ron W.' Colombo at (916)452-3211, extension 4236.
j Sincerely, l
/ 4L t
. Car And 'nini Chief Exec ive Officer, Nuclear l
-Attachments Subscribed and sworn to before me'this.ILl+h day ~of M RU cc:
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