ML20028D951: Difference between revisions

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{{Adams
#REDIRECT [[05000362/LER-1982-007, Forwards LER 82-007/03L-0.Detailed Event Analysis Submitted]]
| number = ML20028D951
| issue date = 01/08/1983
| title = Forwards LER 82-007/03L-0.Detailed Event Analysis Submitted
| author name = Ray H
| author affiliation = SOUTHERN CALIFORNIA EDISON CO.
| addressee name = Engelken R
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
| docket = 05000362
| license number =
| contact person =
| document report number = NUDOCS 8301200113
| package number = ML20028D952
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 2
}}
 
=Text=
{{#Wiki_filter:_                        .
ly Southern California Edison Company                & ,,  ,gCE S AN ONOPRE NUC LF A R GENER A TING S TA TION P.o. som nas p          //
s AN C LEMENTE, C A LIFORNI A 92672 H. B. R A Y                                                                            YELE'"0NE i r A ,,o~ . A . A. A                            January 8,1983                            m m "aa U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region V 1450 Maria Lane, Suita 210 Walnut Creek, California 94596-5368 Attention: Mr. R. H. Engelken, Regional Administrator
 
==Dear Sir:==
 
==Subject:==
Docket No. 50-362 30-Day Report Licensee Event Report No. 82-007 San Onofre Nuclear Generating Station, Unit 3 Pursuant to Section 6.9.1.13.b of Appendix A Technical Specifications to Facility Operating License NPF-15 for San Onofre Unit 3, this submittal provides the required 30-day written report and a copy of Licensee Event Report (LER) for an occurrence involving Limiting Condition for Operation (LCO) 3.4.8.1 associated with Reactor Coolant System (RCS) pressure /
temperature limits.
While in Mode 5 on December 11, 1982, a review of strip chart recordings of the RCS temperature during filling and venting operations performed on December 10, 1982, in accordance with procedure S023-3-1.4 indicated that the RCS heatup rate limits of LC0 3.4.8.1 had been exceeded. As required by the Action Statement associated with this LCO, the RCS heatup rate limits were restored within the allowable 30 minutes.
As corrective action to prevent recurrence, responsible Operations personnel have reviewed the circumstances of this event and have been directed to more closely monitor the RCS vent and fill operations and all other operations involving RCS heatup and cooldown. This will be included in their monthly retraining session. Additionally, 5023-3-1.4 is currently being revised and additional guidance will be incorporated to alert operators of the necessity to closely control heatup and cooldown during filling and venting operations. The attached LER 82-007 addresses this event.
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                                                                                                    ~G_ - 21 82 -@D
 
Mr. R. H. Eng21 ken                                January 8,1983 An engineering evaluation performed as required by the Action Statement of LC0 3.4.8.1 indicated that the effects on structural integrity and the fracture toughness margin were not compromised.
There was no impact on the health and safety of plant personnel or the public associated with this event.
If there are any questions regarding the above, please contact me.
Sincerely, HS % l1%A
 
==Enclosure:==
LER 82-007 cc:  A. Chaffee (USNRC Resident Inspector, San Onofre, Units 2 and 3)
R. Pate (USNRC Resident Inspector, San Onofre, Units 2 and 3)
U.S. Nuclear Regulatory Commission
!                  Office of Inspection and Enforcement' U.S. Nuclear Regulatory Commission Office of Management Information and Program Control Inc,titute of Nuclear Power Operations (INPO) i i                                          .
f f                                                                                    i L}}

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