ML20009C311

From kanterella
Revision as of 00:06, 28 January 2020 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Forwards LER 81-270/03L-0.Detailed Event Analysis Encl
ML20009C311
Person / Time
Site: Oconee Duke Energy icon.png
Issue date: 05/15/1981
From: Parker W
DUKE POWER CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20009C312 List:
References
NUDOCS 8107200453
Download: ML20009C311 (2)


Text

. . .

.  ;; %

DUKE POWER CDMPANY OFFICTAL COPY Q4} fg POWEn I3utto NG 422 SouTn Gnuncis ST,n,zzT, CiuntoTTE, N. C. 28242 s

rs WILLIAM O. PA R M E R. J R.

Tc LgewoN g:Aaga 704

'Mr Pots orut str.- Paoover o~ May 15, 1981 373-4c e s Mr. James P. O'Reilly, Director _

U.S. Nuclear Regulatory Commission Region II /4 j s b

101 Marietta Street, Suite 3100 Q g[ Pr

'*'J-iL 3

Atlanta, Georgia 30303 ,

~

Re: Oconee Nuclear Station .

JUL 1719816 '-

5 , * ** %in 7 4 Docket No. 50-270

Dear Mr. O'Reilly:

ig Please find attached Reportable Occurrence Report R0-270/81-09. This report is submitted pursuant to Oconee Nuclear Station Technical Specifiction 6.6.2.1.b(2), which c.oncerns operation in a degraded mode permitted by a limiting condition for operation, and describes an incident which is con-sidered to be of no significance with respect to its effect on the health and safety of the public.

Ve truly yours, j7

~

/DC 4. /

' William O. Parker, J JLJ:pw Attachment cc: Director Mr. Bill Lavallee Office of Management & Program Analysis Nuclear Safety Analysis Center U.S. Nuclear Regulatory Commission P. O. Box 10412 Washington, D. C. 20555 Palo Alto, California 94303 h

4 h Qt 8107200453 810515 PDR ADOCK 05000270 PDR S

DUKE POWER COMPANY OCONEE UNIT 2 Report Number: R0-270/81-09 Report Date: May 15, 1981 Occurrence Date: April 15, 1981 Facility: Oconee Unit 2, Seneca, South Carolina Ident: ication of Occurrence: '2B' RBCU Inlet Valve Inoperable Conditions Prior to Occurrence: 97% F.P.

Description of Occurrence: At approximately 0930 on April 15, 1981, the monthly Low Pressure Service Water (LPSW) pump periodic test was being i conducted. Upon completion of the Unit 2 test, valves 2LPSW-19 ('2B' RBCU inlet valve) and 2LPSW-21 ('2B' RBCU outlet valve) were closed, thus re-sulting in '2B' RBCU being out of service. At 1600 on April 15, 1981, at the completion of shift turnover, personnel were requested to provide flow through '2B' RBCU. At this time 2LPSW-21 was positioned to provide flow through the '2B' RBCU, and it was noted that 2LPSW-19 was shut. Valve 2LPSW-19 was opened at this time, This incident constitutes operation in a degraded mode per Technical Specification 3.3.5.c and is thus reportable pursuant to Technical Specification 6.6.2.1.b(2).

Apparent Cause of Occurrence: This incident was the result of personnel arror. During test performance, personnel failed to properly note the initial valve position and thus returned valve 2LPSW-19 to the improper position.

Analysis of Occurrence: Sy having 2LPSW-19 shut, the 'J.B' RBCU was in-operable, since 2LPSW-19 is not activated to open under E.S. signal.

Since the other two RBCU's and both building spray trains were operable, the health and safety of general public were not affected.

Corrective Action: The immediate corrective action was to open valve 2LPSW-19. The appropriate personnel involved have been counseled.

.