ML19254F493

From kanterella
Jump to navigation Jump to search
LER 79-083/03L-0:on 791008,during Normal Operation,Routine Computer Printout of Core Performance Log Indicated That Max Fraction of Limiting Power Density Exceeded 1.000. Reactor Power Immediately Reduced 3%
ML19254F493
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 11/05/1979
From: W. Verne Childs
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19254F492 List:
References
LER-79-083-03L, LER-79-83-3L, NUDOCS 7911090529
Download: ML19254F493 (2)


Text

.d HC F UHM ago U. h. WUULt AH H t:tauLAl UH Y CUMMibSION 87 77) 4 - LICENSEE EVENT REPORT CONTROL BLOCK: l l l l l l (PLEASE PRINT OR TYPE ALL REQUIREp INFORMATION) i b 1011l l NIY lJ lA lF l1 l@l0l0l-l0l0 0 0l-l0l0l0l@l4l1l111l1l@l l @

F 8 9 LICENSEE CODE 14 tb LICENSE NuMBEH 25 26 LICENSE TYPE JO $ 7 C A T bd CON'T 0 2 5O[RCE d l0 15DOCK 10ETl0l0 3l3l3l@l1 0l0l8l7 9 l@l 1 l 1 l 0 l 5 l 7 I 980 l@

7 8 60 61 NUMBER 68 63 EVENT DATE 74 75 REPORT DA TE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h fo , . , { SEE ATTACHMENT l 0 l 31 l l O 4 I I O 5 l l 0 6 l l 0 7 I I O s i I 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SU8 CODE COY PONENT CODE SUSCODE SUBCODE 10191 IR Ic l@ LAj@ La_J@ lx lx lx lx lx lx 18 LLl@ LzJ @

SEQUENTI AL OCCURRENCE REPORT REVISION LE R RO EVENT YEAR REPORT NO, CODE TYPE NO.

b aEQ"l, u 17 19

_ 21 22 l-l 2J 1018-13 l 24 26 12.]

27 28 O 3 29 W

30

[--J 31 LOJ 32 TAK A T GN ON PLANT TH HOURS SB IT POR b 8. SUPPLIER MANUFACTUREP lXl@lZl@ lBl@

33 34 35

[Z_j@

30 0 lo 10 0l lY @

41 l42N l@ l l@ [l l l l@

3/ 40 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i O l SEE ATTACHMENT l 1i l t 11 I l i 121 1 I 1 : 131 l l li l4 1I l 7 8 9 80 ST S  % POWE R OTHER STATUS DlS O RY DISCOVERY DESCRIPTION i s

(_E_j @ l1 1 0 l0 l @ l NA J" l A l@l OPERATOR OBSERVATION l

A!TiviTv cO0 TENT RETE ASEo OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE lt l6I W @ [Z__j @ l NA l NA 7 8 9 10 11 44 45 80 PERSONNEL e NPOSunES NUMBER DESCRIPTION li l 7 l l 010 O l@lZ TYPE l

@l NA PsRSONNE t iN;Un'iES - 7 r, -

NUMBER DESCn'7 TION li l a 8l l9 O l 0 l 0 l@l12 11 NA 80 l

7 LOSS OF OR OAVAGE TO FACILITY TYPE DESualPTION l i 198]9l Z l@l10 NA l 7 80 ISSUED QQ QgQ l l l l l y,I ITITI LN_j@ DESCRIPTION l NA l lllllll 4 9 10 68 69 80 E rr,e ChiIds (315) 342-3840 NAME OF PREPAHER . PHON E: {

POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET N0. 50-333 ATTACHMENT TO LER 79-083/03L-0 Page 1 of 1 During normal cperation, operations personnel noted that a routine computer printout of the core performance log indicated that the Maximum Fraction of Limiting Power Density (MFLPD) was 1.014 and 1.016 for two nodes compared to a Technical Specification limit of equal to or less than 1.000. Reactor power was immediately reduced approximately 3% in accordance with the requirements of Technical Specification, Appendix A, Paragraph 4.1.B. This action restored MFLPD to within the limits of Technical Specifications within the time frame allowed and is censidered to be equivalent to operation in a degraded mode. Following the initial power reduction, the control rod pattern was adjusted to reduce local power and power was returned to approximately 100% of rated power three hours later. The event did not represent any significant hazard to the public health and safety.

                                               ~'^7 319 e}}