ML17309A369
| ML17309A369 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/30/1985 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML17309A370 | List: |
| References | |
| LSO5-85-05-036, LSO5-85-5-36, NUDOCS 8506030416 | |
| Download: ML17309A369 (6) | |
Text
REGULATORY 1
ORMATION DISTRIBUTION SYS 5 (RIDS)
ACCESSION NBR;8506030416 DOC ~ DATE: 85/05/30 NOTARIZED!
NO FACIL:50 244 Robert Emmet Ginna Nuclear Plantg Unit ir Rochester G
AUTH~ NAME AUTHOR AFFILIATION ZHOLINSKIg J"JA ~
Operating, Reactors Branch 5
RECIP ~ IIAME RECIPIENT AFFILIATION KOBER t R ~ ii ~
Rochester Gas L Electric Corp.
DOCKET 05000244
SUBJECT:
Forwards revised appliqation for re definition of DISTRIBUTION CODE:
SE01D TITLE:
NRR Correspondence NOTES!NRR/DL/SEP icy, OL:09/19/69 Tech Spec pages 8 safety evaluation re amend to License DPR-18 'mend deletes info hot channel factors, Amend unnecessary.
COPIES RECEI VED ) LTR ENCL "j SIZE ~
re'EP"",Topics h
05000244 RECIPIENT ID CODE/NAME HILLER,C INTERNAL,; ACRS ELD/HDS4 IE/DI DIR IE/DaAVT DIR NRR/
P IAPH 01 ~
EXTERNAL: 24X LPDR NSIC NOTES:
COPIES LTTR ENCL 1
1 10 10 1
~
1 1
1 1
1 1
1 1
1 1
1 1
1 1
RECIPIENT ID CODE/NAME AEOD IE/DEPER-DIR IE/DI/ORPB3 NRR/DL DIR NRR/DL/SEPB RF DIST EX(2 ~ i'>
NRC PDR COPIES LTTR ENCL' 1
1 1
1 1-1 1
30 30.
1 1
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 56 ENCL 56
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,~1 VISITED STAT":S iVUCL~AR REGULATORY COMiv1ISSIOid Ve'ASHINGTON, D. C. 20555 Hay 30, 1985
'r cl,e- "n, 00-~<<
LS05-85-05-035 Iir, ROIIer liI. Rober, Vice President E Ie I.ric and Stean Production Rochester Gas A Electric Corporation 89 East Avenue c~~hes pr New vora'$ 5QG Ioberen Sr p~
bl oy~vT.')"-I E '9" 0" TliFQO'~"
'ON I'ERIAI"> "('
D~"I'I'IDION 0"
HOT CHAI'llIEL FACTORS R.
E.
Ginna Nuclear Power Plant Bv letter da.ed July 17, i984, Rochester Gas and Electric Corporation (RGSE),
submitted a request for an amendment td the R.
E. Ginna Nuclear Power Plant T.chnic<.l Soeci ications
<TS) contained in Appendix A o. Facility Orera+ing
'.=e~se N~
!I-"R-18.
,his reques, was suhr itted to I)rovide coI'sistency
-." -;he bas',s
<or T'.1.
Changes to basis sections of S do ro require license amendments.
The staf< has reviewed the proposed changes tn the basis of TS 2. 1 and as discussed in
.he enclosed Safety Evaluat10n finds them acceptable.
Enclosed are the revised pages which modifies the basis or TS 2. 1 in accordance with your request.
Enclosures:
1.
Pevised Basis Paoes Safe.: Evalua.ion Sincerely,
~a&': I'"" '" '-
John A. Zwo',inski, Chief Opera ing Peactn.
s Branch Division o Licensing cc w/enclosures:
See next page
f::r. Roger I!, Kober
,"cchester Gas a<<'c E'.ectric Co', poration R.
E.
Ginna Nuclear Power Plant CC Harry H. Voigt, Esquire
- LeBoeuf, Lamb, Leibv and HacPae 1333 New Hampshire Avenue, N.l!.
Suite 1100
! ashington, D.C.
20036 Ezra Bialik Assistant Attnrnev General Er~~ ~ronmental Protect'.on Bureau "e;~ York Sta
.. Deoar ment of Law 2 I.'orld Trade Center New York, Hew York 10047 Pesident inspector R.E.
Ginna Plant c/o U.S.
NRC 1503 Lake Road
- Ontario, New York 14519 Stanley B. Vlimbera, Esquire Genera l Counsel New York State Energy 0 fice Agency Building 2
Empire State Plaza
- Albany, Hew York 12223 Regional Administrator Nuclear Regulatory Commission Reoion I 0 ice 631 Park Avenue King of Prussia, Pennsylvania 19406 Supervisor of the Town of Ontario 1850 P,idge Poad On ar io, Hew York 14~19
~ay Dunkleberger Division o Policy Analysis ci Planning New York State Energy Office Agency Building 2
E<<.pire State Plaza
- Albany, Hew York 12223 U. S. Environmental Protection Agency Region Ii Of~ice ATTN:
Regional Padiation Representative 26 Federa]
Plaza New York, New York 10007
Ia q
Ca parameter during reac"o operation.
- herefore, tr ~ observable par=--;:et rs, ihermal powe
, reactor coolant iemperature and pressure
".e "e n "
a=ed io DN~ ihrough the N-3 and/o" FRY-'NB correla-. on.
these DNB correla. 'ons have been developed to predict ihe DNB
=lux and the location of DNB for ax'ally uniform and non-uniform heat flux distribut "ns.
The local DNB heat flux ratio, de ined as ihe raiio of the heai flufi thai would cause Dh'i a pari icu core location io the local heat flux, is indicative of the margin to DS~.
A minimum value o
ihe DNB rai'o, K2iBR, is specified so iha du 'ng sieady state operation, normal operational transients a~d aniicipated iransienis, ther>> is a 95/ probability at a 95/
con
=:dence level thai DNB will not occur.
The curves of
- -igu=e 2.1-i represeni oe loci of points of thermal power, coolant sysiem p"essu"e and average temperaiure for wh'ch this minimum DiiB value is sa i ' fied.
The area oz sa fe opera iion is below these lines.
Since it is possible to have somewhat. greater enthalpy rise hot ch~aael factors at pari power than at full power due to the deepe" control bezZ insertion which is permitted at pari power, a
conservative allowance has been made in obtaining the curves in Fig ~re 2.l-l for an 'ncrease in r<< wi& decreasing power levels.
Rod withdrawal block and load runback occurs be ore reactor trip sei points are reached.
The Reactor Control and Protective Sysiem is designed o prevent any anticipated combination of transient conditions or reactor coolant svsiem temperature, pressure and thermal power level iha 2
0 1 2
Revised R%Y 3 n jg8g
would result in there heing less than a
95% probabili.y at a
95";
l con= d~nc~
leve< tha.
9'~B would not ccc',
(1)
FSAR, Section 3.2.2 (2)
Safetv Evalu-..ion for R.E.
Ginna Transition to 14 x 14 Optimized Fuel Assemb'iies,
'I<e'stinghouse Electric Corporation, November 1983.
2.1-3 Revl sed
"<<l~ 3 ()
1~bo';