ML20009F974: Difference between revisions

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| contact person =  
| contact person =  
| document report number = NUDOCS 8108030210
| document report number = NUDOCS 8108030210
| document type = REPORTABLE OCCURRENCE REPORT (SEE ALSO AO,LER), TEXT-SAFETY REPORT
| document type = REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER), TEXT-SAFETY REPORT
| page count = 1
| page count = 1
}}
}}
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=Text=
=Text=
{{#Wiki_filter:_ _ _ _ - _ _ _ _ _ _
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i                                                                                                                               .-
i I
I M
M q 1 ' LEJ]>y TELECOP'l July 23, 1961 O
q 1 ' LEJ]>y TELECOP'l July 23, 1961 O
/q O'Reilly, Director Y,
O'Reilly, Director                                       Y,           f ,Q     /q Mr. J. P.
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U.S. Nuclear Regulatory Commission                                                   dg                '
" h, Mr. J. P.
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U.S. Nuclear Regulatory Commission
Office of Inspection & Enforcement                                               2 JUL 3 li9BP'hgt 101 11arietta St . , Suite 3100 Atlanta, GA 30303
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Atlanta, GA 30303
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                        'Ihis will confirm a report July 23, 1981                                                                       following end-of-during power escalation         Calculations, At 1225 on July 22, 1081                                                     l cycle control rod withdrawal, SP-312. Heat Ba ance(5, 6, 7, & 8) were less m indicated that all NI's an amount exceeding 0.82.
x gr/
g                                                                                                                   tion
.fic at 0918 to P. J. Kellogg of your-
:naintained was re-Contrary to Technical Specification 3.0.3,                                       the     plant     was in a steady state cond3* ion while                       ~#'   nuclear instrumenta calibrated (SP-113).                                                                 lt of this event.
'Ihis will confirm a report July 23, 1981 following end-of-during power escalation Calculations, At 1225 on July 22, 1081 l
cycle control rod withdrawal, SP-312. Heat Ba ance(5, 6, 7, & 8) were less m indicated that all NI's an amount exceeding 0.82.
:naintained g
Contrary to Technical Specification 3.0.3, the plant was tion was re-in a steady state cond3* ion while nuclear instrumenta
~#'
calibrated (SP-113).
lt of this event.
There was no effect upon the generai'public as a resu (14) days.
There was no effect upon the generai'public as a resu (14) days.
ithin fourteen A detailed report of this event vul f ollow w OY                     .
ithin fourteen A detailed report of this event vul f ollow w OY D. C. Poole Nuclear P3 ant Manager Florida Power Corporation REGIONA DIRECTCR Crystal River, nerid DE D RECTCR DIRECTOR, RRPl DIRECTOR, EPCSDRECT
D. C. Poole Nuclear P3 ant Manager Florida Power Corporation Crystal River , nerid                                                   REGIONA DIRECTCR DE                     D RECTCR DIRECTOR, RRPl
/re OpF\\CE9 E
                                    /re                                                                       DIRECTOR, EPCSDRECT E                    OpF\CE9
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8108030210 e10723 gDRADOCK05000 g
8108030210 e10723 gDRADOCK05000                                                                                                                     g 3}}
3
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Latest revision as of 08:12, 21 December 2024

Ro:On 810722,during Power Escalation Following end-of-cycle Control Rod Withdrawal,Heat Balance Calculations Indicated That All Nuclear Instrumentations 5,6,7 & 8 Were Less Conservative by Amount Exceeding 0.8%
ML20009F974
Person / Time
Site: Crystal River 
Issue date: 07/23/1981
From: Poole D
FLORIDA POWER CORP.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8108030210
Download: ML20009F974 (1)
v • d • e


Text

_ _ _ _ - _ _ _ _ _ _

i I

M q 1 ' LEJ]>y TELECOP'l July 23, 1961 O

/q O'Reilly, Director Y,

f,Q dg

" h, Mr. J. P.

U.S. Nuclear Regulatory Commission

f. JUL 3 li9BP'hgt Office of Inspection & Enforcement 2

Suite 3100 101 11arietta St.,

Atlanta, GA 30303

' ' u s.to E "'

  • q So*

Docker 50-302

]

Licecaee DPR-72 W

R*.:

x gr/

.fic at 0918 to P. J. Kellogg of your-

'Ihis will confirm a report July 23, 1981 following end-of-during power escalation Calculations, At 1225 on July 22, 1081 l

cycle control rod withdrawal, SP-312. Heat Ba ance(5, 6, 7, & 8) were less m indicated that all NI's an amount exceeding 0.82.

naintained g

Contrary to Technical Specification 3.0.3, the plant was tion was re-in a steady state cond3* ion while nuclear instrumenta

~#'

calibrated (SP-113).

lt of this event.

There was no effect upon the generai'public as a resu (14) days.

ithin fourteen A detailed report of this event vul f ollow w OY D. C. Poole Nuclear P3 ant Manager Florida Power Corporation REGIONA DIRECTCR Crystal River, nerid DE D RECTCR DIRECTOR, RRPl DIRECTOR, EPCSDRECT

/re OpF\\CE9 E

C AFFAI b L,)

8108030210 e10723 gDRADOCK05000 g

3

-

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