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123 Main Street V!tute Plains, New York 10601 | 123 Main Street V!tute Plains, New York 10601 | ||
. 914 t?BI 6200 4 NewYo.rkPbwer | |||
4# Authority | ;;;"":=::;. | ||
August 24, 1984 JPN-84-56 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. | 4# Authority | ||
~~- c-- | |||
August 24, 1984 JPN-84-56 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. | |||
20555 Attention:- | |||
Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing | |||
==Subject:== | ==Subject:== | ||
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Mark I Program | James A. | ||
FitzPatrick Nuclear Power Plant Docket No. 50-333 Mark I Program | |||
==Reference:== | ==Reference:== | ||
1. | |||
NRC letter, D. | |||
B. Vassallo to J. P. | |||
: Bayne, dated July 24, 1984. | |||
==Dear Sir:== | ==Dear Sir:== | ||
In Reference 1 the NRC transmitted a request for additional ir formation on the structural aspects of the FitzPatrick plant unique analysis report for torus attached piping. | In Reference 1 the NRC transmitted a request for additional ir formation on the structural aspects of the FitzPatrick plant unique analysis report for torus attached piping. | ||
Attachment I provides the response as requested. | Attachment I provides the response as requested. | ||
If you have any questions concerning this information, please contact Mr. J. A. Gray, Jr. of my staff. | If you have any questions concerning this information, please contact Mr. J. A. Gray, Jr. of my staff. | ||
Very truly yours, J | Very truly yours, J | ||
Irst execu ive Vice President Chief Operations Officer cc: | ayhe. | ||
Irst execu ive Vice President Chief Operations Officer cc: | |||
Office of the Resident Inspector U. S. Nuclear Regulatory Commission P. | |||
O. Box 136 Lycoming, New York 13093 8408310095 840824 PDR ADOCK 05000333 f | |||
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NAMES:A. FITZPATRICK. NUCLEAR POWER PLANT L | |||
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'JAFNPP Torus Program l | |||
LResponse.to: Review Questions on1TES Report | |||
~ | |||
c 4 | :TR-5321-2, PUARLfor Torus Attached Piping 8 | ||
c 4 | |||
~ | |||
' I tem -l ' | |||
In Section 2.4.2 of - the PUA Report, TR-5321-2 (2), some condi-tionsfareclisted that would:be evaluated in case the conserva-tive condition for SRV pipe stress could not be met. Provide the-(reason for considering.the-first of these case:, and: verify the | |||
= value and derivation of; the allowable stress associated : with this case. | |||
Response. The first two ' alternate cases -listed in paragraph | |||
' 2.4.2 are similarfexcept the first includes an OBE seismic event | |||
cases'for-FitzPatrick-.because the FSAR defines' separate spectra for 08E and SSE. That is,' they~ are not simple multiples as- in most -other plants (see paragraph 2.2.5). | -and the.second an-SSE. !They represent cases 14 and 15..in Table 1. | ||
: spectra are different and that SSE has higher damping .that.0BE | It;was judged necessary to consider. both of these as separate cases'for-FitzPatrick-.because the FSAR defines' separate spectra 4 | ||
for 08E and SSE. | |||
That is,' they~ are not simple multiples as-in most -other plants (see paragraph 2.2.5). | |||
The fact that the | |||
: spectra are different and that SSE has higher damping.that.0BE (two percent 'versus 'one per' cent) made2 f t appear. possible that 3 | |||
;responsesLin small frequency bands could be higher.for 08E than | |||
:SSE. -The first alternate load case,''containing.0BE, was_there- | :SSE. -The first alternate load case,''containing.0BE, was_there- | ||
. fore run to cover-this possibility. | |||
3 | 3 The allowable stress for this case is shown in paragraph 2.4.2 as 1.85p This is a typographical error and should have read 1.8 S '- | ||
The allowable stress for this case is shown in paragraph 2.4.2 as | h in accordance with fo,otnote 3 to Table 1 in the TAP report. | ||
. Item 2- | |||
in accordance with fo,otnote 3 to Table 1 in the TAP report. | ~With respect to Section 3.3.5 of the PUA. Report, TR-5321-2 (2), | ||
indicate whether the 10 percent rule of Section 6.2d (1) was used to exempt any branch piping from analysis. If so.-provide calcu-lations demonstrating conformance to this rule. | |||
indicate whether the 10 percent rule of Section 6.2d (1) was used to exempt any branch piping from analysis. If so.-provide calcu- | Also, indicate. | ||
why, in the analysis of flexible branch piping, a displacement equal to the' total torus attached piping motion as the connec-- | why, in the analysis of flexible branch piping, a displacement equal to the' total torus attached piping motion as the connec-- | ||
tion point was used for:the FitzPatrick plant, whereas TES used | tion point was used for:the FitzPatrick plant, whereas TES used | ||
-twice the torus attached piping motion for other plants. | |||
~ | |||
. Response The 10 percent rule was not used to exempt any branch | |||
. piping from analysis. | |||
The analysis of the flexible branch piping for FitzPatrick plant was-performed using twice the torus attached piping motion as it' was for the other plants. The report will be revised to correct thiscin the final issue.- | |||
The analysis of the flexible branch piping for FitzPatrick plant | Item!3 | ||
.WithLrespect to Section 3.4.1 of the PUA Report, TR-5321-2 (2), | |||
was for the other plants. The report will be revised to correct thiscin the final issue.- | l'- | ||
Item!3 | indicate whether seismic loads were considered in load cases 25 and 151(Table 1). | ||
l'- | |||
l' | l' | ||
,4 a | ,4 a | ||
- - ~.. | |||
.. - _....., _,, - _. - -. _ _.,-... -. - _... ~.1 | |||
e JAFNPP Torus Program Response to Reviev Questions on TES Report TR-5321-2, PUAR for Torus Attached Piping Response The larger of the Oi.E or SSE seismic stress was in- | e JAFNPP Torus Program Response to Reviev Questions on TES Report TR-5321-2, PUAR for Torus Attached Piping Response The larger of the Oi.E or SSE seismic stress was in-cluded in the evaluation of load cases 25 and 15 (Table 1). Both seismic events were considered for the reasons discussed in Item 1 above. | ||
cluded in the evaluation of load cases 25 and 15 (Table 1). Both seismic events were considered for the reasons discussed in Item 1 above. | Item 4 With respect to Tables 3-1 and 3-2 of the PUA Report, TR-5321-2 (2), indicate whether the lines in each of the following sets are identical and explain why only one result appears for each set. | ||
Item 4 | X-202A and X-202F, X-202B and X-202G, X-210A and X-211A, X-210B | ||
identical and explain why only one result appears for each set. | ) | ||
X-202A and X-202F, X-202B and X-202G, X-210A and X-211A, X-210B and X-2118, X-213A and X-213B, and A-206A, B, C, and D. | and X-2118, X-213A and X-213B, and A-206A, B, C, and D. | ||
Response Lines X-202A and F are connected by a comon system in a single analytical model. A single analysis was performed and 4 | |||
Response Lines X-202A and F are connected by a comon system in | only the maximum stress results are reported. | ||
a single analytical model. A single analysis was performed and | Lines X-202B and G are similar in configuration and in analysis l-method to that used in X-202A and F. | ||
Lines X-202B and G are similar in configuration and in analysis | \\ | ||
Lines X-210A and X-211A are connected by a cross-over system in a i~ | |||
Lines X-210A and X-211A are connected by a cross-over system in a | single analytical model. | ||
single analytical model. A single analysis was performed and | A single analysis was performed and only the maximum stress results are reported. | ||
only the maximum stress results are reported. | Lines X-210B and X-211B are similar in configuration and in l-analysis method to that used in X-210A and X-211A. | ||
Lines X-210B and X-211B are similar in configuration and in | Lines X-213A and B are identical and only the maximum stress results of one system are reported. | ||
Lines X-213A and B are identical and only the maximum stress results of one system are reported. | .= | ||
Lir.es X-206A, B, C, and D are two similar systems where X-206A | Lir.es X-206A, B, C, and D are two similar systems where X-206A and " are connected by a comon piping system and X-206C and D are identical to X-206A and B. | ||
and " are connected by a comon piping system and X-206C and D | Only the maximum stress results from one system are reported. | ||
are identical to X-206A and B. Only the maximum stress results | Item 5 With respect to Section 3.4.6 of the PUA Report, TR-5321-2 (2), | ||
from one system are reported. | I provide the analytical results of the fatigue evaluation of the b | ||
Item 5 | torus shell penetrations. | ||
Response The usage factor "u" is used to determine the fatigue acceptability. This is calculated as | Response The usage factor "u" is used to determine the fatigue acceptability. | ||
This is calculated as Maximum number of cycles possible Number of allowable cycles at S t | |||
Appendices | a The allowable number of cycles at S is calculated according to ASME Section III, NE-3221.5, and uses Table I-9 in the Appendices. | ||
+ | |||
V JAFNPP Torus Prograa J'''' | |||
Response to Review Questions on TES Report-TR-5321-2, PUAR for Torus | |||
__ [ | __ [ | ||
Attached Piping i | Attached Piping i | ||
I I | |||
The maximum number of full stress cycles was conservatively | The maximum number of full stress cycles was conservatively 1 | ||
taken as 10,000 as discussed in the PUAR (2), paragraph 3.4.6. | |||
(The actual number of full stress cycles is actually. about 1,000.) | (The actual number of full stress cycles is actually. about 1,000.) | ||
.; 8ased on a.1 assumed 10,000 full stress cycles, the three highest usage factors for lar e bore pipe penetrations (as tabulated in Table 3-6 of the PUAR are: | |||
Large Bore Penetration Usage Factors Cycles | Large Bore Penetration Usage Factors Cycles Penetration Assumed Allowable Usage Factor X-212 10,000 12,000 0.83 X-225A 10,000 21,000 0.48 j | ||
Penetration | X-2108 10,000 23,200 0.43 - | ||
All small bore penetrations have usage factors less than 0.01. | All small bore penetrations have usage factors less than 0.01. | ||
r A | r A | ||
M | M e | ||
4}} | E 4}} | ||
Latest revision as of 09:13, 13 December 2024
| ML20096A395 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick |
| Issue date: | 08/24/1984 |
| From: | Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| JPN-84-56, NUDOCS 8408310095 | |
| Download: ML20096A395 (5) | |
Text
-
123 Main Street V!tute Plains, New York 10601
. 914 t?BI 6200 4 NewYo.rkPbwer
- ""
- =
- ;.
4# Authority
~~- c--
August 24, 1984 JPN-84-56 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention:-
Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing
Subject:
James A.
FitzPatrick Nuclear Power Plant Docket No. 50-333 Mark I Program
Reference:
1.
NRC letter, D.
B. Vassallo to J. P.
- Bayne, dated July 24, 1984.
Dear Sir:
In Reference 1 the NRC transmitted a request for additional ir formation on the structural aspects of the FitzPatrick plant unique analysis report for torus attached piping.
Attachment I provides the response as requested.
If you have any questions concerning this information, please contact Mr. J. A. Gray, Jr. of my staff.
Very truly yours, J
ayhe.
Irst execu ive Vice President Chief Operations Officer cc:
Office of the Resident Inspector U. S. Nuclear Regulatory Commission P.
O. Box 136 Lycoming, New York 13093 8408310095 840824 PDR ADOCK 05000333 f
PDR gh P
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LResponse.to: Review Questions on1TES Report
~
- TR-5321-2, PUARLfor Torus Attached Piping 8
c 4
~
' I tem -l '
In Section 2.4.2 of - the PUA Report, TR-5321-2 (2), some condi-tionsfareclisted that would:be evaluated in case the conserva-tive condition for SRV pipe stress could not be met. Provide the-(reason for considering.the-first of these case:, and: verify the
= value and derivation of; the allowable stress associated : with this case.
Response. The first two ' alternate cases -listed in paragraph
' 2.4.2 are similarfexcept the first includes an OBE seismic event
-and the.second an-SSE. !They represent cases 14 and 15..in Table 1.
It;was judged necessary to consider. both of these as separate cases'for-FitzPatrick-.because the FSAR defines' separate spectra 4
for 08E and SSE.
That is,' they~ are not simple multiples as-in most -other plants (see paragraph 2.2.5).
The fact that the
- spectra are different and that SSE has higher damping.that.0BE (two percent 'versus 'one per' cent) made2 f t appear. possible that 3
- responsesLin small frequency bands could be higher.for 08E than
- SSE. -The first alternate load case,containing.0BE, was_there-
. fore run to cover-this possibility.
3 The allowable stress for this case is shown in paragraph 2.4.2 as 1.85p This is a typographical error and should have read 1.8 S '-
h in accordance with fo,otnote 3 to Table 1 in the TAP report.
. Item 2-
~With respect to Section 3.3.5 of the PUA. Report, TR-5321-2 (2),
indicate whether the 10 percent rule of Section 6.2d (1) was used to exempt any branch piping from analysis. If so.-provide calcu-lations demonstrating conformance to this rule.
Also, indicate.
why, in the analysis of flexible branch piping, a displacement equal to the' total torus attached piping motion as the connec--
tion point was used for:the FitzPatrick plant, whereas TES used
-twice the torus attached piping motion for other plants.
~
. Response The 10 percent rule was not used to exempt any branch
. piping from analysis.
The analysis of the flexible branch piping for FitzPatrick plant was-performed using twice the torus attached piping motion as it' was for the other plants. The report will be revised to correct thiscin the final issue.-
Item!3
.WithLrespect to Section 3.4.1 of the PUA Report, TR-5321-2 (2),
l'-
indicate whether seismic loads were considered in load cases 25 and 151(Table 1).
l'
,4 a
- - ~..
.. - _....., _,, - _. - -. _ _.,-... -. - _... ~.1
e JAFNPP Torus Program Response to Reviev Questions on TES Report TR-5321-2, PUAR for Torus Attached Piping Response The larger of the Oi.E or SSE seismic stress was in-cluded in the evaluation of load cases 25 and 15 (Table 1). Both seismic events were considered for the reasons discussed in Item 1 above.
Item 4 With respect to Tables 3-1 and 3-2 of the PUA Report, TR-5321-2 (2), indicate whether the lines in each of the following sets are identical and explain why only one result appears for each set.
X-202A and X-202F, X-202B and X-202G, X-210A and X-211A, X-210B
)
and X-2118, X-213A and X-213B, and A-206A, B, C, and D.
Response Lines X-202A and F are connected by a comon system in a single analytical model. A single analysis was performed and 4
only the maximum stress results are reported.
Lines X-202B and G are similar in configuration and in analysis l-method to that used in X-202A and F.
\\
Lines X-210A and X-211A are connected by a cross-over system in a i~
single analytical model.
A single analysis was performed and only the maximum stress results are reported.
Lines X-210B and X-211B are similar in configuration and in l-analysis method to that used in X-210A and X-211A.
Lines X-213A and B are identical and only the maximum stress results of one system are reported.
.=
Lir.es X-206A, B, C, and D are two similar systems where X-206A and " are connected by a comon piping system and X-206C and D are identical to X-206A and B.
Only the maximum stress results from one system are reported.
Item 5 With respect to Section 3.4.6 of the PUA Report, TR-5321-2 (2),
I provide the analytical results of the fatigue evaluation of the b
torus shell penetrations.
Response The usage factor "u" is used to determine the fatigue acceptability.
This is calculated as Maximum number of cycles possible Number of allowable cycles at S t
a The allowable number of cycles at S is calculated according to ASME Section III, NE-3221.5, and uses Table I-9 in the Appendices.
+
V JAFNPP Torus Prograa J'
Response to Review Questions on TES Report-TR-5321-2, PUAR for Torus
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Attached Piping i
I I
The maximum number of full stress cycles was conservatively 1
taken as 10,000 as discussed in the PUAR (2), paragraph 3.4.6.
(The actual number of full stress cycles is actually. about 1,000.)
.; 8ased on a.1 assumed 10,000 full stress cycles, the three highest usage factors for lar e bore pipe penetrations (as tabulated in Table 3-6 of the PUAR are:
Large Bore Penetration Usage Factors Cycles Penetration Assumed Allowable Usage Factor X-212 10,000 12,000 0.83 X-225A 10,000 21,000 0.48 j
X-2108 10,000 23,200 0.43 -
All small bore penetrations have usage factors less than 0.01.
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