ML17251A618
| ML17251A618 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/24/1986 |
| From: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Lear G Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM NUDOCS 8603310097 | |
| Download: ML17251A618 (7) | |
Text
j~
REGULATORY ORMATION DISTRIBUTION SY (RIDS)
ACCESSION NBR: 86033100'P7 DOC. DATE: 86/03/24 NOTARIZED:
NO
'OCKET 0 FACIL: 50-244 Robert Emmet Ginna Nuclear Planti Unit li Rochester G
05000244 AUTH. NAME AUTHOR AFFILIATION KOBERi R. N.
Rochester Gas 5 Electric Corp.
REC IP. NAME RECIPIENT AFFILIATION LEARN G. E.
PWR Prospect Directorate 1
SUBJECT:
Advises that mod to insulation on pressurizer relief valve loop seals rescheduled for Spring 1987 outagei due to lead time required +or procurement oF engineered items. Mod responds to NUREG-0737 Item II. D. 1 DISTRIBUTION CODE:
A046D COPIES RECEIVED: LTR ENCL SIZE:
TITLE:
OR Submittal:
TMI Action Plan Rgmt NUREG-0737 5 NUREG-0660 NOTES: License Exp date in accordance with 10CFR2> 2. 109(9/19/72).
05000244 RECIPIENT ID CODE/NAME PNR-A ADTS PNR-A EICSB PNR;A PD1 PD 01 PNR-A PSB INTERNAL: ADM/LFMB IE/DEPER DIR 33 NRR BWR ADTS NRR PNR-A ADTS NRR/
T R
G F 04 COPIES LTTR E 1
2 5
1 1
1 1
1 1
1 CL RECIPIENT ID CODE/NAME PNR-A EB PNR-A FOB FAIRTILEe M PWR-A RSB ELD/HDS4 IE/DEPER/EPB NRR PAULSONi N.
NRR PWR-B ADTS NRR/DSRO EMRIT RGN1 COPIES LTTR ENCL EXTERNAL: 24X NRC PDR
,02 LPDR NSI C TOTAL NUMBER OF COPIES REQUIRED:
LTTR 31 ENCL
( BGI R) ii:.',YB NO1TUu> RTBIQ NOXTAMRO'RQTPJUQ3P, T " A~'lG Pbc 0"OCO GN "Q3EIRA'TON
&~ >COXGF,;37/'G.ZQG
'cPOOr 6=-068 c
'redye ri 30R a r
+ L rrU sv ci&X i
'rci 3 I Jul'c EarrrriQ d'emm3 d'r so oR NOITAIJI"",RA ROHY" 'A
.q~oQ oivd)sI3 P
c'
~ef~erl~aR Na>~AI JI=l=cA rN3I9I03R i..d'avodoov'Q
., >el,os9 RA>
"RflN NC'Ic c'3" fik~~3-3r~.JI.AR HYr~vl f"TUA R
c R3GD"-'.
.3M4',! 9't 3" 3
'3.0
~ RA3J "f,"'OOG' evxrv %eire~ aaXi ruea~ieq no rrosdr luvni od born drcrld aseivhA
-TQ3L PUB beeI od sub csosduo
%"39l pni vqB 'ru4 beluberl.~<" ew 'sse qooe boM>>meJ i beqssrrt prrs
'}n drrsrne~u>oqq
.ro1 bsaiuyev emid r.0.II medI ciG70-03RUN od abrroq;.ez 3~ IB J3N3 Riw (G3VI303R B3I I'33 QdPcOi~:3GQD t~<<lI'l'UtiIRTBIG CA&0-03RUN 0 c'P'0-Q3RUN dmpR rtsecl rroidoA IMT:LrddimouB RD
.3JTIT
.(<'CXPeXP)EOe.B,c R'930i r<+kcu aa<vsbzo" vc,, rri edrb qx3
'.n)ar.].B3lL"'l PBI IOD JDN3 RTTJ I
0 C
E' e
r e
TN3 I'LI03R 3MANX3QDO GX 83 A-.el*;!"l 80'9 A-R M c3JIYRXA=l GBcR A-b>l9
-MQHXG l3 69 gyR3c<3QX3 I
.(J.NQB lU+9 flRN PTQrq P.-fl'89
>IRN
'r I HI('I:l ORBQX RRN e "l~)R 0
e r
TN3I 9 I33R 3MANX3GOD QI BTQA A."WMcl GBOI3 A
RW9
$ 0 Q9 eG9 A-RM9 HB9 P -'RM9 HMRJXI"lGA 'JANR3 < NI CC RIG R393QX3I c.'TQA RMH RR'"
BTGA A-PvJ9 PR~
T~HQXf'l~ i~
00 3JI=l 03R e
e 1;
<<JQRJ OIP.N 0
Xbc~
JvNR3Ti(2 RG9 DRN
I'IIIIIRIII//SPS ES II SSSÃ ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 ROGER W. KOBER VICE PRESIDENT ELECTRIC &STEAM PRODUCTION March 24 I 1986 TELEPHONE AREA coDE Tld 546-2700 Director of Nuclear Reactor Regulation Attention:
Mr. George E. Lear> Chief PWR Project Directorate No.
1 U.S. Nuclear Regulatory Commissi'on Washington>
D.C.
20555
Subject:
NUREG-0737I Item II.D.l Relief and Safety Valve Performance R.
E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Lear:
By letter dated May 24I 1985I Rochester Gas and Electric responded to NRC Staff requests for additional information on testing of relief and safety valves.
In our response to Question lli we indicated that a modification to the insulation on the pressurizer relief valve loop seals would be performed during the Spring>
1986 outage.
Howeveri due to the lead time required for procurement of the engineered items>
and the scope of other outage activitesi this modification was not performed.
It has been rescheduled for the Spring 1987 outage.
The continued operation of Ginna prior to completion of these modifications is acceptable for the following reasons.
The EPRI testsi upon which the safety valve piping analysis was based>
used two widely separated loop seal temperature profiles.
The "hot o loop seal" test used a minimum temperature of approximately 350 Pi with the "cold loop seal" test using essentially ambient temperatures.
No tests were conducted at temperatures between those two conditions.
While the temperature measurements of the Ginna loop seal were in total inconclusivei a majority of the loop seal vo'lume was measured at a temperature most consistent with the hot loop seal case.
As a resultr forces generated in downstream piping would also closely represent those in the hot loop seal case used in the Ginna piping analysis.
The effect on downstream piping from the small volume of water in the loop seal in which the temperature could not be verified to be "hot" would not be expected to inhibit safety valve operation or compromise primary system integrity.
V truly yours>
86033l 0097 860324 PDR ADOCK 95000244 P
PDR Ro er W. Kober
i l
lf I
l l
'v 1
t I
i 1
L(
March 18, 1986 DOCKET NO(S).
50-244 Mr. Roger ll. Kober Vice President Electtic and Steam Production Rochester Gas It'lectric Corporation 89 East Avenue Rochester, New York 14649 R. E.
GONNA NUCLEAR POWER PLANT I
Distribution:
Oocket File w/o Encl. ~
PAD81 R/F w/o Encl.
P. Shuttleworth w/Encl.
Ginna PM w/Encl.
The following documents concerning our review of the subject facility are transmitted for your information.
D Notice of Receipt of Application, dated D Draft/Final Environmental Statment, dated D Notice of Availabilityof Draft/Final Environmental Statement, dated D Safety Evaluation Report, or Supplement No.
, dated D Notice of Hearing on Application for Construction Permit, dated D Notice of Consideration of Issuance of Facility Operating License, dated D Monthly Notice; Applications and Amendments to Operating Licenses Involving no Significant Hazards Considerations, dated D Application and Safety Analysi's Report, Volume D Amendment No.
to Application/SAR dated D Construction Permit No. CPPR-D Facility Operating License No.
, Amendment No.
, Amendment No.
dated
, dated D Order Extending Construction Completion Date, dated QXOther (Speci fy) e d Januar 15 1986.
Ex iration date
Enclosures:
As stated See next page 14 1986.
Division of PWR Licensing-A Office of Nuclear Reactor Regulation OPFelCEW SURNAME~
PAM1:JA...
P. Shuttle orth
~ W18/86....
NRC FORM 318 t1/84) NRCM 0240
Cr E"
~
~ l'4
~
~ 4,
<<)
I hl
~.
~
~
~
~
~ ~
4 h
~
=l
~
0 c
Rochester Gas and Electric Corporation R.
E. Ginna Nuclear Power Plant CC:
Harry H. Voigt, Esquire
- LeBoeuf, Lamb, Leiby and MacRae 1333 New Hampshire
- Avenue, N.W.
Suite 1100 Washington, D.C.
20036 Ezra Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Resident Inspector R.E.
Ginna Plant c/o U.S.
NRC 1503 Lake Road
- Untario, New York 14519 Stanley B. Klimberg, Esquire General Counsel New York State Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Regional Administrator, Region I U.S. Nuclear Regulatory Commission
$ 31 Park Avenue King of Prussia, Pennsylvania 19406 Supervisor of the Town of Ontario 1850 Ridge Road