ML20039D408
| ML20039D408 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 12/22/1981 |
| From: | Baskin K SOUTHERN CALIFORNIA EDISON CO. |
| To: | Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.D.2, TASK-2.B.3, TASK-2.F.1, TASK-2.K.2.19, TASK-2.K.3.30, TASK-TM NUDOCS 8201040064 | |
| Download: ML20039D408 (3) | |
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S A P. T Y, AND LICE N$iNQ n
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Director, Office of Nuclear Reactor Regulation 1
Attention: Mr. Frank Miraglia, Branch Chief RECEiM 7 f
Licensing Branch No. 3 C
l U. S. Nuclear Regulatory Conimission 2-Jg4 1982Wf s
Washington, D.C.
20555 p meJR l.
,,,,g i,,, g N u g ',,. 1 Gentlemen:
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Subject:
Docket Nos. 50-361 and 50-362
'd San Onofre Nuclear Generating Station Units 2 and 3 s
The purpose of this letter is to discuss the TMI Action Items for which San Onofre Units 2 and 3 implementation is projected to be completed af ter the schedule indicated in NUREG-0737 " Clarification of TMI Action Plan Requirements". These items we e discussed previously in the NRC/SCE management meeting on December 3, 1981.
Please find attached, 63 copies of a table entitled " Outstanding TMI Action Items", dated December 21, 1981.
This table identifies the NRC schedule date, S:n Onofre Units 2 and 3 implementation schedule, the basis for the implementation schedule and justification for the acceptability of the implementation schedule for each of the subject itens.
If there are any questions or comments regarding the attached, i
please contact me.
Very truly yours, 7^,xx&A Attachment I
8201040064 811222 l
PDR ADOCK 05000361
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1-W cenber 21. 1981 1
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SAN ONOFRE UNITS 2 AND 3 t
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OUTSTANDING TMI ACTION ITEMS y
NRC Implementation Scheduled Background for\\
Justification for item No.
Subject Date and Source Implementation Date.
Inpl emanta. idn
,,(.
Implementat' ion t
Schedule i
Schedule e
J.D.2 Plant Safety Undefined in NUREG C696 1s t.Re fuelin g '
Requirements were Safety Par.3ineters are Parameter Display initially defined adequately dis;iUfed Console in NUREG 0696 on other easily.. /
published in Feb. 1981.
accessable :entrol Detailed specifitaticas room indicat'on.
The for SPDS have been critical func. tion '
- lmonitMjngsystem defined to satisfy I 0696 requiremeats provided in response,
and initial purchase /,
'tto item III. A.1.2 orders for equipment will provide adc-quste have been.placed.
moeiter',ng of plant-
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safety, status untfI Plant c fety Parareter e
( Display c,*nsole is
[
' installed.
II.B.3 Post Accident 1/1/82 per NUREG 0737 Prior to OPS Delays in detailed > system Sufficient fission Sampling System or above 5% power material deli.very have product inventory to (PASS) 5% power level reulted in implementation warran't the:use of per SER (NUREG 0712) schedule delays.
this syster,in the Supplement #1 event of an accident will not exist before s
operrtion above 5%
power.
I I.F.1 Noble Gas (wide 1/1/82 per NUREG 0737 Prior to OPS Determination of qualified Sufficient fission Attachments #1 range) Ef fluent or above 5% power source and material product inventory to ard #2 Monitor 5% power level delivery delays have warrant the use of and per SER (NUREG 0712) resulted in reschedule these monitors in the Iodine /
Supplement #1 of implementation.
event of an accident will not exist before Particulate Isokinetic operations above 5%
Samplers p owe r.
December 21, 1981 SAN ON0FRE UNITS 2 AND 3 OUTSTANDING TMI ACT_ ION ITEMS NRC Implementation Scheduled Background for Justification for Item No.
Subject Date and Source Implementation Date Implementation Implementation Schedule Schedule ll.K.2.19 Sequential 1/1/82 per NUREG 0737 N/A Sequential auxiliary feedwater flow analytical Auxiliary Feed-requirements are only of concern to once-through water Flow steam generator designs. Since CE utilizes Analysis inverted U-tube steam generator designs, requirements set forth in this item have been determined to be not applicable to NSSS systems designed by Combustion Engineering.
(Ref:
St.
Lucie II SER-NUREG 0843 page 22-29)
II.K.3.30 Revised Small 1/1/82 per NUREG 0737 3/31/82 CE Owners Group is Engineering evaluation Break LOCA presently reviewing only.
No plant Analytical Model and modifying the modi fications generic analytical model anticipated.
and has requested relief until 3/31/82 4
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