ML060950253
| ML060950253 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 03/31/2006 |
| From: | Pace P Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TAC MC8305 | |
| Download: ML060950253 (25) | |
Text
- ':
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 MAR 3 1 2006 10 CFR 50.55a U.
S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C. 20555-0001 Gentlemen:
In the Matter of
)
Docket No. 50-390 Tennessee Valley Authority WATTS BAR NUCLEAR PLANT (WBN)
UNIT 1 -
AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)
SECTION XI INSERVICE PRESSURE TESTING PROGRAM REQUEST FOR RELIEF ISPT-09 (TAC NO. MC8305)
The purpose of this submittal is to provide TVA's response t:o NRC's request for additional information dated February 3, 2006 concerning the subject relief request.
The Enclosure provides TVA's response to this request.
There are no regulatory commitments associated with this submittal.
If you have any questions concerning this matter, please call me at (423) 365-1824.
Sincerely, P..ace Manager, Site Licensing and Industry Affairs Enclosure cc:
See Page 2 V4M7
U.S. Nuclear Regulatory Commission Page 2 MIAR 31 2006 Enclosure cc (Enclosure):
NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 Mr. D. V. Pickett, Senior Project Manager U.S. Nuclear Regulatory Commission MS 08G9a One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI REQUEST FOR RELIEF ISPT-09 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION NRC QUESTION 1 Relief Request (RR) No. ISPT-09 requests relief from the requirements of the American Society of Mechanical Engineers (ASIE') Boiler and Pressure Vessel Code, Division 1 (henceforth Section XI), Table IWB-2500-1, Examination Category B-P, based on the hardship provisions that are specified in Paragraph (a)(3)(ii) of Title 10 of the Code of Federal Regulations.
Specify which Edition of Section XI is the Code of record for Watts Bar Nuclear Plant, Unit 1 (WBN-1).
In addition, specify which. Inspection Items in Section XI Table IWB-2500-1, Examination Category B-P are applicable to the piping segments that are within the scope of the relief request, as identified in Table 1, "Piping Segment Descriptions," of the Enclosure to the relief request.
TVA RESPONSE The Code of Record for the WBN First Inservice Inspection Interval is the 1989 Edition of ASME Section XI.
Applicable inspection items for the piping segments are Item No.
B15.51 for the piping itself and Item No. B15.71 for the valves contained within and establishing the boundary of each piping segment.
NRC QUESTION 2 Reference the basis (e.g., Academic Textbook, ASME Section XI paragraph, NUREG Report, etc.) for the following equation that is specified on Page E-4 of the RR No. ISPT-09 submittal:
L; = LXI X ( PS, / PXz )I/
TVA RESPONSE The basis for the equation Lp = Lxz X (Pp / PxI)112 is the ASME Operation and Maintenance (OM) Standard 10, paragraph 4.2.2.3(b)(4) which provides guidance for correction of valve seat leakages to full functional differential pressure for tests that are performed at reduced pressures.
OM-10, paragraph 4.2.2.3.(B)(4) states that leakage is proportional to the ratio E-1
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI REQUEST FOR RELIEF ISPT-09 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION of the test differential pressure to the full functional differential pressure raised to the 1M power.
In the case of pressure testing of piping, the applicable pressures are reduced test pressure Pp and the Code specified test pressure PxI.
NRC QUESTION 3 The relief request proposes to perform the required hydrostatic pressure tests of the ASME Code Class 1 piping segments at test pressures lower than those that are required in Section XI Table IWB-.5220-1, which is called out by reference in Section XX Paragraph IWB-5222(a).
Confirm that the alternative pressure tests proposed in RR No. ISPT-09 will be subject to the minimum hold times that are required by Section XI Paragraph IWA-5213 for hydrostatic pressure tests and the minimum test temperatures that are required by Section XI Article 5000 (e.g., the minimum temperature requirements in Paragraph IWB-5230 in Editions through the 1992 Edition or in Paragraph IWB-5240 in the 1995 Edition and more recent Editions).
TVA PESPONSE The minimum hold time required by ASME Section XI paragraph IWA-5213(d) for system hydrostatic tests will be observed.
The minimum test temperature requirements of ASME Section XI paragraph IWB-5230 will be applied.
These hold times and temperatures are implemented in the implementing instruction for the 10-year hydrostatic pressure test.
NRC QUESTION 4 Table 1, "Piping Segment Descriptions," of the Enclosure to hR:
No. JSPT-09 (i.e., the enclosure to the Tennessee Valley Authority letter of September 8, 2005) provides the descriptions of the piping segments that are within the scope of the relief request.
The staff seeks the following clarifications for the piping segments descriptions that are provided in Table 1:
E-2
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI REQUEST FOR RELIEF ISPT-09 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Note:
In the following clarifications, the word "inboard" refers to the end of the boundary that is nearest to the reactor core and the word "outboard" refers to the end of the boundary that is furthest from the reactor core.
- a.
Reactor Coolant Loop 1 on Page E-7:
"Low pressure safety injection from RHR system CKV-63-633 to the 10-inch Loop 1 cold leg injection line." Clarify which component in the 10-inch Loop 1 cold leg injection line bounds the end of the piping segment that requires pressure testing.
TVA RESPONSE The 10-inch Loop 1 cold leg injection line adjoined by this 6-inch branch connection is the second item in the listing of Loop 1 pipe segments and is bounded by CKV-63-622 and CKV-63-560.
This 6-inch branch connection begins at outboard check valve CKV-63-633 and continues inboard to the point where it joins the 10-inch Loop 1 cold leg injection line.
ISPT-09 Table 1 has been resorted to group the piping segment descriptions so that the interconnected segments are grouped together rather than by the RCS Loop to which the pipe attaches.
This should clarify the scope and boundaries of the piping segments involved.
The table has also been revised to indicate the appropriate drawing number and Updated Final Safety Analysis (UFSAR) Figure number which are attached for convenience.
- b.
Reactor Coolant Loop 1 on Page E-7:
"High pressure safety injection piping from the 3-inch common header from CKV 581 to Loop 1 cold leg piping to CKV-63-586." Confirm that the component description should be "High pressure safety injection piping from CKV-63-581 in the 3-inch common header to CKV-63-586 in the Loop 1 cold leg piping."
TVA RESPONSE This piping segment does not run from CKV-63-581 to CKV 586.
The high head safety injection piping between the inboard and outboard check valves is described in four segments, one for each loop.
The common piping, which begins at CKV-63-581 and continues through the 2M-inch and 3-inch headers, is included with the segment containing the E-3
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI REQUEST FOR RELIEF ISPT-09 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION llh-inch branch line to Loop 3. This piping segment is a lh-inch branch connection that begins at Loop 1 inboard check valve, CKV-63-586, and continues outboard to the point where it joins the 3-inch supply header coming from CKV-63-581.
The 3-inch supply header to which this branch is adjoined is the 3-inch portion of the fourth item down in the Loop 3 grouping of pipe segments.
The 3-inch supply header is also part of the segment discussed in Item 4.j of this response.
ISPT-09 Table 1 has been resorted to group the piping segment descriptions so that the interconnected segments are grouped together rather than by the RCS Loop to which the pipe attaches.
This should clarify the scope and boundaries of the piping segments involved.
The table has also been revised to indicate the appropriate drawing number and UFSAR Figure number which are attached for convenience.
- c.
Reactor Coolant Loop 1 on Page E-7:
"Safety injection pump piping from CKV-63-543 to the 8-inch Loop 1 hot leg injection line." Clarify which component in the 8-inch Loop 1 hot leg injection line bounds the end of the piping segment.
TVA RESPONSE The 8-inch Loop 1 hot leg line adjoined by this 2-inch branch connection is the last piping segment in the listing of Loop 1 piping segments and is bounded by CKV-63-640 and CKV-63-641.
This 2-inch branch connection begins at outboard check valve CKV-63-543 and continues inboard to the point where it joins the 8-inch residual heat removal (RHR) hot leg injection piping.
ISPT-09 Table 1 has been resorted to group the piping segment descriptions so that the interconnected segments are grouped together rather than by the RCS Loop to which the pipe attaches.
This should clarify the scope and boundaries of the piping segments involved.
The table has also been revised to indicate the appropriate drawing number and UFSAR Figure number which are attached for convenience.
- d.
Reactor Coolant Loop 1 on Page E-7:
"Safety injection pump piping from CKV-63-551 to the 6-inch Loop 1 cold leg injection line." Clarify which component in the 6-inch Loop E-4
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI REQUEST FOR RELIEF ISPT-09 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION 1 cold leg injection line bounds the end of the piping segment.
TVA RESPONSE The 6-inch Loop 1 cold leg injection line is the third item down in the Loop 1 grouping of pipe segments and is bounded by CKV-63-633.
The 6-inch Loop 1 cold leg injection line, which is discussed in Item 4.a of this request, connects to the 10-inch cold leg accumulator (CLA) 1 discharge line that is the second item down in the Loop 1 grouping of pipe segments and is bounded by CKV-63-622 and CKV-63-560.
The segment discussed in this item is a 2-inch branch connection beginning at outboard check valve, CKV-63-0551, and continuing inboard to the point where it joins the 6-inch Loop 1 cold leg injection line.
ISPT-09 Table 1 has been resorted to group the piping segment descriptions so that the interconnected segments are grouped together rather than by the RCS Loop to which the pipe attaches.
This should clarify the scope and boundaries of the piping segments involved.
The table has also been revised to indicate the appropriate drawing number and UFSAR Figure number which are attached for convenience.
- e.
Reactor Coolant Loop 2 on Page E-8:
"Low pressure safety injection from RPR system CKV-63-632 to the 10-inch Loop 2 cold leg injection line." Clarify which component in the 10-inch Loop 2 cold leg injection line bounds the end of the piping segment.
TVA RESPONSE The 10-inch Loop 2 cold leg injection line adjoined is the second item in the listing of Loop 2 pipe segments and is bounded by CKV-63-623 and CKV-63-561.
This piping segment is a 6-inch branch connection beginning at outboard check valve CKV-63-632 and continuing inboard to the point where the segment joins the 10-inch piping coming from CLA 2.
ISPT-09 Table 1 has been resorted to group the piping segment descriptions so that the interconnected segments are grouped together rather than by the RCS Loop to which the pipe attaches.
This should clarify the scope and boundaries of the piping segments involved.
The table has also been.
E-5
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI REQUEST FOR RELIEF ISPT-09 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION revised to indicate the appropriate drawing number and UFSAR Figure number which are attached for convenience.
- f.
Reactor Coolant Loop 2 on Page E-8:
"High pressure safety injection piping from the 3-inch common header from CKV 581 to Loop 2 cold leg piping to CKV-63-587." Confirm that the component description should be "High pressure safety injection piping from CKV-63-581 in the 3-inch common header to CKV-63-587 in the Loop 2 cold leg piping."
TVA RESPONSE This piping segment does not run from CKV-63-581 to CKV 587.
The high head safety injection piping between the inboard and outboard check valves is described in four segments, one for each loop.
The common piping, which begins at CKV-63-581 and continues through the 2%-inch and 3-inch headers, is included with the segment containing the 1lh-inch branch line to Loop 3. This piping segment is a 1h-inch branch connection that begins at the Loop 2 inboard check valve CKV-63-587 and continues outboard to the point where it joins the 3-inch supply header coming from CKV-63-581.
The 3-inch supply header to which this branch is adjoined is the 3-inch portion of the fourth item down in the Loop 3 grouping of pipe segments.
The 3-inch supply header is also part of the segment discussed in Item 4.j of this response.
ISPT-09 Table 1 has been resorted to group the piping segment descriptions so that the interconnected segments are grouped together rather than by the RCS Loop to which the pipe attaches.
This should clarify the scope and boundaries of the piping segments involved.
The table has also been revised to indicate the appropriate drawing number and UFSAR Figure number which are attached for convenience.
- g.
Confirm that the Loop 2 piping segment descriptions on page E-8 should not include an entry from a check valve in the Safety Injection pump piping to a valve in an 8-inch or 6-inch Loop 2 hot leg injection line in the manner they have been included for Reactor Coolant System Loops 1, 3, and 4.
If the Loop 2 entries should include such a piping segment description and the entry has not been included in Table 1, please amend Table 1 to add it.
If the Loop 2 entries in Table 1 do include such a piping segment entry, please E-6
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI REQUEST FOR RELIEF ISPT-09 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION identify which entry contains the applicable component description.
TVA RESPONSE The words "Loop 2 hot leg injection line" were not included in the Loop 2 segment containing CKV-63-547 and CKV-63-559.
However, this piping segment is in fact the hot leg injection supply from the Safety Injection Pumps.
The segment consists of 2-inch and 6-inch piping, with the transition to 6-inch piping being made less than a foot before the piping joins inboard check valve CKV-63-559.
ISPT-09 Table 1 has been resorted to include a specific reference to the Safety Injection Pumps in this segment identifier for clarity.
The table has also been revised to indicate the appropriate drawing number and UFSAR Figure number which are attached for convenience.
- h.
Reactor Coolant Loop 2 on Page E-8:
"Safety Injection pump piping from CKV-63-553 to the 6-inch Loop 2 cold leg injection line." Clarify which component in the 6-inch Loop 2 cold leg injection line bounds the end of the piping segment.
TVA RESPONSE The 6-inch Loop 2 cold leg injection line (the third item down in the Loop 2 grouping of pipe segments) is bounded by CKV-63-632.
The 6-inch RHR branch connection connects to the 10-inch CLA 2 discharge line (the second item down in the Loop 2 grouping of pipe segments) which is bounded by CKV-63-623 and CKV-63-561.
The segment of piping discussed here is a 2-inch branch connection beginning at outboard check valve CKV-63-553 and continuing inboard to the point where it joins the 6-inch Loop 2 cold leg injection line.
The 6-inch Loop 2 cold leg injection line is discussed in.
Item 4.e of this response.
ISPT-09 Table 1 has been resorted to group thelpiping segment descriptions so that the interconnected segments are grouped together rather than by the RCS Loop to which the pipe attaches.
This should clarify the scope and boundaries of the piping segments involved.
The table has also been.
E-7
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI REQUEST FOR RELIEF ISPT-09 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION revised to indicate the appropriate drawing number and UFSAR Figure number which are attached for convenience.
- i.
Reactor Coolant Loop 3 on Page E-9:
"Low pressure safety injection from RHR system CKV-63-634 to the 10-inch Loop 3 cold leg injection line." Clarify which component in the 10-inch Loop 3 cold leg injection line bounds the end of the piping segment.
TVA RESPONSE The 10-inch Loop 3 cold leg injection line adjoined is the second item in the listing of Loop 3 pipe segments and is bounded by CKV-63-624 and CKV-63-562.
This piping segment is a 6-inch branch connection beginning at outboard check valve CKV-63-634 and continuing inboard to the point where it joins the 10-inch Loop 3 cold leg injection line.
ISPT-09 Table 1 has been resorted to group the piping segment descriptions so that the interconnected segments are grouped together rather than by the RCS Loop to which the pipe attaches.
This should clarify the scope and boundaries of the piping segments involved.
The table has also been revised to indicate the appropriate drawing number and UFSAR Figure number which are attached for convenience.
- j.
Reactor Coolant Loop 3 on Page E-9:
"High pressure safety injection piping from CKV-63-581 to Loop 3 cold leg piping to CKV-63-588." Confirm that the component description should be "High pressure safety injection piping from CKV-63-581 in the 3-inch common header to CKV-63-588 in the Loop 3 cold leg piping."
TVA RESPONSE This piping segment is high pressure safety injection piping and does run from CKV-63-581 to CKV-63-588.
The high head safety injection piping between the inboard and outboard check valves is described in four segments, one for each loop.
The common piping, which begins at CKV-63-581 and continues through the 21h-inch and 3-inch headers, is included with this segment, which also contains the Wl-inch branch line to Loop 3. The other three piping segments are I%-inch branch connections that begin at their respective!
RCS loop inboard check valves (CKV-63-586, -587, and -58.)
E-8
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI REQUEST FOR RELIEF ISPT-09 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION and continue outboard to the point where the segments join the 21h-inch and 3-inch supply headers coming from CKV-63-581 that are contained in this piping segment.
The other three 1',-inch branch lines are discussed in Items 4.b, 4.f, and 4.n of this response.
ISPT-09 Table 1 has been resorted to group the piping segment descriptions so that the interconnected segments are grouped together rather than by the RCS Loop to which the pipe attaches.
This should clarify the scope and boundaries of the piping segments involved.
The table has also been revised to indicate the appropriate drawing number and UFSAR Figure number which are attached for convenience.
- k.
Reactor Coolant Loop 3 on Page E-9:
"Safety injection pump piping from CKV-63-545 to the 8-inch Loop 3 hot leg injection line."
Clarify which component in the 8-inch Loop 3 hot leg injection line bounds the end of the piping segment.
TVA RESPONSE The 8-inch Loop 3 hot leg injection line adjoined is the last piping segment in the listing of Loop 3 piping segments and is bounded by CKV-63-643 and CKV-63-644.
This segment of piping is a 2-inch branch connection beginning at outboard check valve CKV-63-545 and continuing inboard to the point where it joins the 8-inch Loop 3 hot leg injection line.
ISPT-09 Table 1 has been resorted to group the piping segment descriptions so that the interconnected segments are grouped together rather than by the RCS Loop to which the pipe attaches.
This should clarify the scope and boundaries of the piping segments involved.
The table has also been revised to indicate the appropriate drawing number and UFSAR Figure number which are attached for convenience.
- 1.
Reactor Coolant Loop 3 on Page E-9:
"Safety injection pump piping from CKV-63-555 to the 6-inch Loop 3 cold leg injection line." Clarify which component in the 6-inch Loop 3 cold leg injection line bounds the end of the piping segment.
E-9
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI REQUEST FOR RELIEF ISPT-09 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION TVA RESPONSE The 6-inch Loop 3 cold leg injection line is the third item down in the Loop 3 grouping of pipe segments and is bounded by CKV-63-634.
It is also discussed in Item 4.i of this response.
The 6-inch Loop 3 cold leg injection line connects to the 10-inch CLA 3 discharge line bounded by CKV-63-624 and CKV-63-562.
The 10-inch CLA 3 discharge line is the second item down in the Loop 3 grouping of pipe segments.
The piping segment addressed by this item is a 2-inch branch connection beginning at outboard check valve CKV-63-555 and continuing inboard to the point where it joins the 6-inch Loop 3 cold leg injection line.
ISPT-09 Table 1 has been resorted to group the piping segment descriptions so that the interconnected segments are grouped together rather than by the RCS Loop to which the pipe attaches.
This should clarify the scope and boundaries of the piping segments involved.
The table has also been revised to indicate the appropriate drawing number and UFSAR Figure number which are attached for convenience.
- m.
Reactor Coolant Loop 4 on Page E-10:
"Low pressure safety injection from RHR system CKV-63-635 to the 10-inch Loop 4 cold leg injection line." Clarify which component in the 10-inch Loop 4 cold leg injection line bounds the end of the piping segment.
TVA RESPONSE The 10-inch Loop 4 cold leg injection line is the second item in the listing of Loop 4 pipe segments and is bounded by CKV-63-625 and CKV-63-563.
The piping segment discussed in this item is a 6-inch branch connection beginning at outboard check valve CKV-63-635 and continuing inboard to the point where it joins the 10-inch Loop 4 cold leg injection line.
ISPT-09 Table 1 has been resorted to group the piping segment descriptions so that the interconnected segments are grouped together rather than by the RCS Loop to which the pipe attaches.
This should clarify the scope and boundaries of the piping segments involved.
The table has also been revised to indicate the appropriate drawing number and UFSAR Figure number which are attached for convenience.
E-10
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI REQUEST FOR RELIEF ISPT-09 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION
- n.
Reactor Coolant Loop 4 on Page E-10:
"High pressure safety injection piping from the 3-inch common header from CKV 581 to Loop 4 cold leg piping to CKV-63-589." Confirm that the component description should be "High pressure safety injection piping from CKV-63-581 in the 3-inch common header to CKV-63-589 in the Loop 4 cold leg piping."
TVA RESPONSE This piping segment does not run from CKV-63-581 to CKV 589.
The high head safety injection piping between the inboard and outboard check valves is described in four segments, one for each loop.
The common piping, which begins at CKV-63-581 and continues through the 2h-inch and 3-inch headers, is included with this segment, containing the 1'A-inch branch line to Loop 3.
The piping segments discussed here is the l'A-inch branch connection that begins at the Loop 4 inboard check valves, CKV-63-589, and continues outboard to the point where the segment joins the 3-inch supply header coming from CKV-63-581.
The 3-inch supply header to which this branch is adjoined is the 3-inch portion of the fourth item down in the Loop 3 grouping of pipe segments.
The 3-inch supply header is also part of the segment discussed in Item 4.j of this response.
ISPT-09 Table 1 has been resorted to group the piping segment descriptions so that the interconnected segments are grouped together rather than by the RCS Loop to which the pipe attaches.
This should clarify the scope and boundaries of the piping segments involved.
The table has also been.
revised to indicate the appropriate drawing number and UFSAR Figure number which are attached for convenience.
- o.
Reactor Coolant Loop 4 on Page E-10:
"Safety injection pump piping from CKV-63-557 to the 6-inch Loop 4 cold leg injection line."
Clarify which component in the 6-inch Loop 4 cold leg injection line bounds the end of the piping segment.
TVA RESPONSE The 6-inch Loop 4 cold leg injection line is the third item down in the Loop 4 grouping of pipe segments and is bounded by CKV-63-635.
The 6-inch Loop 4 cold leg injection line is also discussed in Item 4.m of this response.
The 6-inch E-ll
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI REQUEST FOR RELIEF ISPT-09 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION Loop 4 cold leg injection line in turn connects to the 10-inch CLA 4 discharge line that is bounded by CKV-63-625 and CKV-63-563.
The 10-inch CLA 4 discharge line is the second item down in the Loop 4 grouping of pipe segments.
The segement of piping discussed in this item is a 2-inch branch connection beginning at outboard check valve CKV-63-557 and continuing inboard to the point where it joins the 6-inch Loop 4 cold leg injection line.
ISPT-09 Table 1 has been resorted to group the piping segment descriptions so that the interconnected segments are grouped together rather than by the RCS Loop to which the pipe attaches.
This should clarify the scope and boundaries of the piping segments involved.
The table has also been revised to indicate the appropriate drawing number and UFSAR Figure number which are attached for convenience.
- p.
Reactor Coolant Loop 4 on Page E-10:
"RHR piping between FCVs-74-1 and 8 and FCVs-74-2 and 9." The staff reconmmends that the pipe segment description be broken into two separate entries because it is confusing exactly which flow control valves are the valves that bound the length of the piping segments.
TVA RESPONSE Flow Control Valves, FCVs-74-1 and -2 are the preferred valves to be opened to establish a suction connection to the RCS during the shutdown process.
Each valve is provided with a bypass valve [FCVs-74-8 and -9 respectively]
installed in parallel with the preferred valve that can be opened by operator action if one of the preferred valves fail to open.
The four valves are required to describe the boundary of this piping segment.
FCVs-74-1 and -9 provide the inboard boundary and FCVs-74-2 and -8 provide the outboard boundary.
See attached UFSAR Figure 5.5-3-1 (TVA Drawing No. 1-47W810-1).
E-12
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PIPING SEGMENT DESCRIPTIONS Safety injection Accumulator No. 1 outlet isolation valve to outlet check valve (FCV-63-118 to CKV-63-622)
(Ref: C/N 83015; Dwg. E-2879 IC-89) 23 610-660 10 140 Safety injection Accumulator No. 1 outlet check valve to Loop 1 cold leg (CKV-63-622 to CKV-63-560)
(Ref: C/N 83015; Dwg. E-2879 IC-89) 18 SA-376 Type 316 l
6-inch branch connection from the 10-inch Safety Injection Accumulator 1 outlet piping to the low pressure safety injection (RHR system) check valve CKV-63-633 (Ref: C/N 83015; Dwcg. E-2879 IC-89) 2485 6
23 1500 160 1-2-inch branch connection from the 6inch RHR system branch to the Safety Injection System check valve CKV-63-551 (Ref: Weld Map 435-7 Sheet 2) 2 10 SA-376 Type 304 E-13
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 REQUEST FOR RELIEF ISPT-09 RESDPONSE TO DREQTTES FOR AnnD 7MTh nMTTC TnD TOn
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- SA Safety injection Accumulator No. 2 out isolation valve to outlet check valve (FCV-63-98 to CKV-63-623)
(Ref: C/N 83015; Dwg. E-27879 IC-90) 140 16 610-660 10 Safety injection Accumulator No. 2 outlet check valve to Loop 2 cold leg (CKV-63-623 to CKV-63-561)
(Ref: C/N 83015; Dwg. E-27879 IC-90)
SA-376 Type 316 2485 15 1500 6-inch branch connection from the 10-inch Safety Injection Accumulator 2 outlet piping to the low pressure 6
12 SA-376 safety injection (RHR system) check Type 316 valve CKV-63-632 160 2485 1500 (Ref: C/N 83015; Dwg.
E-27879 IC-90) 160 2485 1500 2-inch branch connection from the 6-inch RHR system branch to the Safety 2
21 SA-376 Injection System CKV-63-553 Type 304 (Ref: Weld Map 435-8 Sheet 6)
E-14
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 REQUEST FOR RELIEF ISPT-09 RESPONSE TO REQUEST FOPR ADDITIONAL ITFOTPMATIOr.m p.i..........................
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l-¢-iemete:r Pip tet ILength aal tip e Ressuorel Pr~ess, Dec:t o (ichs Sc ed l (fet Mae.a
-p (psig)
-- ::::::::: ::::.::::g::::::
E.6 3-1 SH 1
.VA
.....IN............
Safety injection Accumulator No. 3 outlet isolation valve to outlet check valve 9
610-660 (FCV-63-80 to CKV-63-624)
(Ref: C/N 83015; Dwg. E-2879 IC-91) 10___140__
Safety injection Accumulator No. 3 outlet 1
4 check valve to Loop 3 cold leg (CKV-63-624 17 to CKV-63-562)
SA-376 (Ref: C/N 83015; Dwg. E-2879 IC-91)
Type 316 6-inch branch connection from the 10-inch Safety Injection Accumulator 3 2485 outlet piping to the low pressure 1
safety injection (RHR system) check 6
171500 valve CKV-63-634 (Ref: C/N 83015; Dwg. E-2879 IC-91) 160 2-inch branch connection from the 6-inch RHR system branch to the Safety SA-376 Injection System check valve 2
20 Type 304 CKV-63-555 (Ref: Weld Map 435-9 Sheet 4)
E-15
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 REQUEST FOR RELIEF ISPT-09 ML~OnnAMTCLI M(
n~fnTTVL'1P VID 7%
TrnThnmTC'hTT TTATnD?.R, rrTn7Th i.......
_..1,1 1 1 1
1=
De t
nj io crilton E
(inches)ip Sc hedule (fet Maio-al terial (psig (plt Sig)
~~~~~~~....,......,,
Safety injection Accumulator No.
4 outlet isolation valve to outlet check valve 2261-0 (FCV-63-67 to CKV-63-625)
(Ref: C/N 83015; Dwg. E-2879 IC-92) 1 4
Safety injection Accumulator No. 4 outlet 1
4 check valve to Loop 4 cold leg (CKV-63-625 2
to CKV-63-563) 24SA-376 (Ref: C/N 83015; Dwg. E-2879 IC-92)
_____Type 316 6-inch branch connection from the 20-inch Safety injection Accumulator 4 2485 outlet piping to the low pressure 6
21 safety injection (RHR system) check 61500 valve CKV-63-635 (Ref: C/N 83015; Dwg. E-2879 IC-92) 160 2-inch branch connection from the 6-inch RHR system branch to the Safety SA-376 Injection System check valve 2
7Type 304 CKV-63-557 (Ref: Weld Map 435-6 Sheet 9)
E-16
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 REQUEST FOR RELIEF ISPT-09 PVCnnlTTCV' MrA DUrrnTTVCrnm rVn(D AnnTMT(T rT. T nTrTVrDMArpTn(T SsJa_,Jvow. vJl s Go Ad.
a_ fi.
sI.s
- 4..
4.
High pressure safety injection piping from CKV-63-581 to Loop 3 cold leg injection check valve CKV-63-588 (Ref: C/N 83015; Dwg. E-2879 IC-86; Weld Map 435-9 Sheet 2) 3 2'A l'A 11A-inch branch connection from the 3-inch common header coming from CKV-63-581 to Loop 1 cold leg injection check valve CKV-63-586 (Ref: Weld Maps 435-6 Sheet 3 and 435-7 Sheets 16-17; 47W435-7) l1h-inch branch connection from the 3-inch common header coming from CKV-63-581 to Loop 4 cold leg injection check valve CKV-63-589 (Ref: Weld Map 435-6 Sheet 4) 160 SA-376 Type 304 2485 1500 1A l'h-inch branch connection from the 2%-
inch common header coming from CKV-63-581 to Loop 2 cold leg injection check valve CKV-63-587 (Ref: Weld Maps 435-8 Sheet 14 and 435-9 Sheet 1)
I I
E-17
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 REQUEST FOR RELIEF ISPT-09 PRREPONS TO REQUTEST FOP ADnTTnITCTMAT T %TL0MATION bOW pressure saLeiy injection Lrom AHA system CKV-63-640 to the Loop 1 hot leg injection CKV-63-641 (Ref: C/N 83015; Dwg. E-2879 IC-54) 8 29 2
6 160 SA-376 Type 304 2485 1500 2-inch branch connection from the 8-inch RHR piping to Safety Injection System Check Valve CKV-63-543 TWor1 7,an AtZE-7 0C--i-fi 2
5 noUw preLssUre SUecy inJecLion LrOm Anr system CKV-63-643 to the Loop 3 hot leg injection CKV-63-644
[Reduces to 6" NPS at the inlet to CKV-63-644J (Ref: C/N 83015; Dwa. E-2879 IC-55) 8 42 160 SA-376 Type 304 2485 1500 4
2-inch branch connection from the 8-inch RHR piping to Safety Injection System Check Valve CKV-63-545 (Ref: Weld Map 435-8 Sheet 9) 2 7
_________________________ 2 ___________________
__________________ 1 _____________________ 1 __________________________.1. _____________________________
E-18
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 REQUEST FOR RELIEF ISPT-09 RESPONSE TO REQUEST FOR ArDDTTTONAT. TWMPMATTrO Safety Injection pump piping from CKV-63-547 to CKV-63-559 (Ref: C/N 83015, Dwg. E-2879 IC-90; Weld Map 435-8 Sheet 13) olft-o I U Type 304 zareLy +/-L1]ecCLoU pUL Pump p.Lp.Lly rLLIm V-O.-
to CKV-63-558 in the 6 inch Loop 4 hot leg injection line (Ref: C/N 83015; Dwg. E-2879 IC-92; Weld Map 435;-6 he 1) 6 rom.check...valv
{.
gz of. thes.Follc 2
6
-2.......
Xg -of£ tWh'e Fol3;'
5 10 1
10 160
- 0. 5 1SA-376 0 Type 316 49 to..the.-Reactor..Co
~~........ ^v:,...............
Sements.
E44 SA-376 Type 304 2485 1500 160 0.5 SA-376 Type 316 2485 1500 Kxn" p.LP.L1n JJC:wuue r,-v- /4 Imana 1tS; JJYpas valve FCV-74-9) and FCV-74-2 (and its bypass valve FCV-74-8)
(Ref: C/N 83015; DWG. E-2879 IC-53) 22 140 50 I
SA-376 Type 316 2485 350 14 1-U+/-L+/-La.Ly spr.Lay PLp+/-Liny LLUILL r
-r%.-.V-V4-0-1 through 1-CKV-62-661 (Ref: C/N 83015; Dwg. E-2879 IC-36; Weld Map 406-9, Sheet 17; 47W406-7 & -8) 3 160 41 SA-376 Type 304 2485 325 to 2235 E-19
ENCLOSURE ATTACHMENT WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 REQUEST FOR RELIEF ISPT-09 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION UFSAR FIGURE 9.3-15 SH 1 (TVA DRAWING 1-47W809-1)