ML18019B149

Submits Addl Info Re Instrumentation to Detect Inadequate Core Cooling,Per SER License Condition 8.Instrumentation Includes Subcooling Margin Calculated by Emergency Response Facilities Info Sys Computer & Core Exit Thermocouple Sys

ML18019B149
Person / Time
Site:	Harris
Issue date:	08/29/1986
From:	Zimmerman S CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NLS-86-332, NUDOCS 8609080045
Download: ML18019B149 (4)

Text

REGULATO INFORNATION DISTRIBUTION 'TEN (RIDB)

ACCESSION NBR: 8b09080045 DOC. DATE: 86/08/29 NOTARIZED: NO DOCKET ¹ FACIL: 50-400 Shearon HaY ris Nuclear Power Planti Unit ii Carolina 05000400 AUTH. NANE AUTHOR AFFILIATION ZINNERNANi S. R. Carolina Power Zc Light Co.

RECIP. NANE RECIPIENT AFFILIATION DENTON> H. R. Office of Nuclear Reactor Regulationi Director (post 85ii25

SUBJECT:

Submits addi info re instrumentation to detect inadequate core coolingi per SER License Condition 8. Instrumentation includes subcooling margin calculated bg emergency response facilities info sos computer 5 core exit thermocouple sos.

DISTRIBUTION CODE: AOOSD COPIES RECEIVED: LTR l ENCL Q. SIZE:

TITLE: OR Submittal: Inadequate Core Cooling (Item II. F. 2) QL 82-28 NOTES:Application for permit renewal filed. 05000400 RECIPIENT COPIES RECIP IENT COP 1EB ID CODE/Nhl'1E LTTR ENCL ID CODE/MANE LTTR ENCL PWR-A PD2 LA PWR-A PD2 PD BUCNLEY, B PWR-A RBB INTERNAL: ADN/LFNB NRR BWR DIR i NRR BWR PDi i NRR PWR-A DIR i NRR PWR-B DIR i NRR SHEAz J Oi ENRI T i NRR/DBRO/RSIB i EQ F 04 i RQN2 07 i EXTERNAL: LPDR 03 NRC PDR 02 NSIC Oh TOTAL NUMBER OF COPIES REQUIRED: LTTR i9 ENCL

<>tJT',"TP,lG t~O'LT~"."r3'0'r jt jg r)iver) 3 T."~'I') r.'"'0)~

N ~'~%60%66 .3T ~Q,>Or I ~Or)brir3>>, 066,'3I8N Nr33;.,'.;,,

P, 0 '79QJo9 "rsvp oirN c~ g'rQ QH I'Q'~g ~3 it4 (3(36 r 'a" . IK <<)g4 1-I~01 ":ik.lf.tIA $ li!II'rJ~> It~i,', i I-ll'4,

.oQ "II,~3 i" r >'au'I ~~ii <<o

."IQI'I'A>> I k 9 Ih Tt'i If ~i:)'l>t

~ ~

),'R 'i'!~iAYrl,it'l'.>

INK~'.1 .<<i3.:) IR P:~ 5 f('iCr 8 c'o rl) 'Toz 3:>'Tir~ ~rro r,d'8 fvpr R ~o+~L.sR -",<<of guN !o .~ << IN.> .H .I ,'.I~tO r;~i.-3'".

~.v'sutr') bsn~ '> )o 49b oS fraid 68n3friu59'Br< L <<2'7 O-I'iiE Lbl)r " xmrtu '14>~trP i;cifsdrio >>> rJ:.rrT, .8 rro~fzbnoD gens >~ I H I:, raq <>tirxfoa'->>

O~naq'~ )a 1rari >p jme ud b~adafuzfr O nip VCm rtniiaaai'u~~ . <<~buf>rr>>

pa zf qrro ~omr rtf 8 L'>s ovoa P eetuqmav orr~ ~':Ini ~oi difi ~i~')

-IXX' ~ IQM3 RT'3:QBVI3D3R HBf~t(33 VQOGA:BOO:3 IX)3'TtlrfIRT~'6

&~i'-'.~Q tt) (" . I .XT msd13 pni tool evan sdauyabr~irf fi' l-fmituU >IV .3 I 1.1 ~

Oot (30(3e0 bof i% f s. >>rr'.> r fin>>.sq ~~'-3 no i.,) i f qq(>.b'." <"'!l'i f 'll):) TNG ERE ...7R -'ar Ia..> SI Y~R J 3,".t9 ~lT I I -ktlANXHat:1 3 OI JDWJ H'1 I' 4'if~N~.MGf'> 3 AK 0 I <(I GBR RM "'IH

]

Hf 0 A-RM9 PRN (4-h-HW9

'It,i9 RRN jjVi'If Cj A r .':lu'< A 4,V;I Iltboq Ht'r l.lht'I(t~>; Jh',~r,'

't" <<I ARN I,', ~ F 4O L <<A3FB RRN H X(1 g-Ate"3 HHNr GiHRXAR 'GXRRN TfRNR QHPr'iXRRN

'RNQR l,l @0 i',.g tX'-I Q-]H g

~

(3 f. RQ I I ~

Ir~t)R

ggQ[l Carolina Power & LIght Company SERIAL: NLS-86-332 AUG 2 9 1986 IMr. Harold-R. Denton,.Director .

Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 DOCKET NO.50-000 INADEQUATE CORE COOLING INSTRUMENTATION

Dear Mr. Denton:

Carolina Power R Light Company (CPRL) hereby submits additional information concerning the Shearon Harris Nuclear Power Plant (SHNPP) instrumentation to detect inadequate core cooling. This information is submitted in response to Safety Evaluation Report (SER) License Condition No. 8. The instrumentation to detect inadequate core cooling includes the following three subsystems: (1) subcooling margin calculated by the Emergency Response Facilities Information System (ERFIS) Computer, (2) core exit thermocouple system, and (3) Reactor Vessel Level Instrumentation System (RVLIS).

This instrumentation will be installed and preoperational testing completed prior to fuel load. Portions of RVLIS which require data from actual reactor coolant flow measurements with the core in place will be tested after fuel load. The above commitments supplement CPRL's previous commitments on this instrumentation submitted by letter dated May 29, 1986.

If you have any questions or require additional information on this subject, please contact me at (919) 836-6202.

Yours very truly, S. Z erman Manager Nuclear Licensing Section 3HE/crs (0072GAS) cc: Mr. B. C. Buckley (NRC)

Mr. G. F. Maxwell (NRC-SHNPP)

Dr. J. Nelson Grace (NRC-RII) 8609080045 860829

'PDR E

kDOCK 05000400

, PDR os I

g 411 Fayetteville Street + P. O. 8ox 1551 ~ Raleigh. N. C. 27602

't 0

Hf V