ML17256A644
| ML17256A644 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/22/1983 |
| From: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM NUDOCS 8304270080 | |
| Download: ML17256A644 (11) | |
Text
REGULATORY FORMATION DISTRIBUTION S EM (RIDS)
ACCESSION NBR;8304270080 DOG ~ DATE: 83/04/22 NOTARIZED:
NO DOCKET'0 FACIL:50 244 Rober t Emme,t Ginna Nuclear Planti Uni,t ii Rochester G
05000244 AUTH BYNAME AUTHOR AFFILIATION MAIERpJ ~ E ~
Rochester Gas L.Electric.Corp,
'R EC IP ~ NAME RECIPIENT AFFILIATION CRUTCHF IELD g D ~
Oper at1ng Reactors Branch 5
SUBJECT:
Forwards Pages 47p48i49 8
59 from repts submitted 830304 re pressurizer relief 5 safety valves~per NUREG 0737/
Item IIoDii.
DISTRIBUTION CODE:
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5'ITLE:
OR Submittal:
TMI Action Plan Rgmt NUREG-0737 5
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eeee ERASE ROCHESTER GAS AND ELECTRIC CORPORATION
~ 89 EAST AVENUE, ROCHESTER. N Y. 14649 JOHN E MAIER Vice Presklent TELEPHONE AREA coDE Tle 546.2700 April 22, 1983 Director of Nuclear Reactor Regulation Attention:
Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No.
5 U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Post-TMI Requirements, NUREG 0737, ITEM II.D.l R. E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Crutchfield:
By letter dated March
~ 4,,1983, we submitted two reports addressing the "pressurizer relief and safety valves.
'In, response to a request from a'member of your staff, copies of pages 47, 48, 49 a'nd 59 are enclosed to replace the incomplete copies provided in our initial submittal.
Enclosures Very truly yours, g~ tule~
John E. Maier 8304270080 830422 PDR *DOCK 05000244 P.:,,
PDR s
4
5.2. 3 EMERGENCY CONDITIONS The combined stresses due to primary loadings of pressure,
- weight, and safety valve thrust, using applicable stress intensification factors, must not exceed the allowable limits.
The magnitud of the resultant moment~ ";, is calculated from the moment components as shown below:
Mi
+
M
+
M
+
M
+
M
+
xSOT "wt ySOT yw SOT E
E E
where M,M,M xwt ywt wt
= deadwei ght moment components M,M, M
= safety line operation moment components xSOT ySOT
'SOT 5.2.4 FAULTED CONDITIONS The combined stresses due to the primary loadings of pressure,
- weight, saf shutdown earthquake (SSE),
and SOTF, using applicable stress intensification factors, must not exce d the allowable limits.
The magnitud of the resultant moment, Mi, is calculated from the three moment components as shown below:
(N 2
+
~
)
1/2
~
~
2 SOTF SSE w
c 2
2 1/2 M
+
M
+
ysoT yssE F
ywt 0514s:10 Ae
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+
2 2
1/2 M
+
M
)
+
SOT F
'SSE wt 2
1/2 where M, N, N
"wt ywt deadwei ght moment compon en ts M,N, M
SSE moment components SSE ySSE SSE N, -M, M
= maximum of SOTU and SOTE moment components SOT ySOT SOT For the safety and relief piping, the faulted condition load coobination of pressure,
- weight, and valve thrust is considered as given in Tables 2-1 and 2-2 and defined in Table 2-3.
The pipe break loads (MS/FWPB or LOCA) can be and were ignored for the PSARV system.
These loads have very little impact on the pressurizer safety arid relief system when compared to the loading conditions discussed in this report.
5.3 SECONOARY STRESS EVALUATION The combined str esses due to all thermal
- loadings, using applicable stress intensification factors, must not exceed the allowable limit of SA for thermal only or (Sh
+ SA) for.thermal, pressure, and
" I'~>i,c>4~r""
weight.
For the resultant moment loading, M;, thermal moments are combined as shown below:
N.
=
N
-N 2
+
M N
2
+
M
- M 2
1/2 MAX MIN yMAX yN IN MAX MIN Nx; M, Mz maximum thermal moment considering all thermal cases NAX NAX NAX incl uding normal operation z
minimum thermal moment considering all thermal cases NIN yNIN NIN incl uding normal operation 0514s:10
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SECTION 6
RESULTS I'.1 EVALUATION PRIOR TO EPRI TEST PROGRAM The R. E. Ginna relief valve discharge piping system had received a very detailed thermal hydraulic and structural dynamic evaluation to ensure the operability and structural integrity of the system prior to this evaluation.
This structural evaluation, including the thermal hydraulic
- analysis, was based on the criteria and methods that were current prior to the availability of the data from the EPRI Test Program.
Design analyses were also conducted on the safety valve discharge piping.
Thermal hydraulic forcing functions were generated for different cases that define potential environments under which the relief valves could open.
Simultaneous opening of all relief valves was one of the cases considered.
The forcing functions from all cases were then used as input to the structural evaluation in which the primary and secondary stresses were determined.
The methods used and the loadings considered are consistent with Section 2.0 and Section 3.0 of this report, respec-
'tively.
Results of this extensive analysis and evaluation have demon-strated that the PSARV piping meets all the applicable design limits for the various loading cases subsequent to relief valve discharge.
In
- addition, the acceptability of the valve nozzles, equipment nozzles, and pressurizer shell was assured for the applied loads.
6.2 EVALUATION SUBSEquENT To Et RI TEST PROGRAM The R. E. Ginna pressurizer safety and relief valve discharge piping system has received a detailed thermal hydraulic analysis and structural evaluation to ensure the operability and structural integrity of the system.
The methods used and the, loadings considered are consistent with Sections 2, 3, 4, and 5 of this report.
0514s:10
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TABLE 6-2 HYDRAULIC FORCES RELIEF LINE Force No.
Force (LBF)
Force No.
For ce LBF) 1 2
3 4
5 6
7 8
9 65 80 180 765 1020 375 160 125 175 10 11 12 13 14 15 16 17 18 795
'60'95 400 80 135 110 205 390 The force numbers correspond to the sement nuober on Figure 4-2.
0514s:10 0
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