NL-05-135, Indiana Point, Unit 2, Response to Request for Additional Information Regarding Relief from System Hydrostatic Test Requirements for Large Bore Pipe (RR-74/MC7307)
| ML053490119 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 12/05/2005 |
| From: | Conroy P Entergy Nuclear Northeast |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-05-135, TAC MC7307 | |
| Download: ML053490119 (8) | |
Text
Enterav Nuclear Northeast Indian Point Energy Center 450 Broadway Buchanan, NY 10511-0249
'-Entergy Patric Conroy Licensing Manager Tel (914) 734 6668 December 5, 2005 Re: Indian Point Unit 2 Docket No. 50-247 NL-05-135 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Response to Request for Additional Information Regarding Relief from System Hydrostatic Test Requirements for Large Bore Pipe (RR-741 MC7307)
References:
- 1. Entergy letter NL-05-073 to NRC, dated June 8, 2005; "Request for Relief from System Hydrostatic Test Requirements for Large Bore (> 1 inch)
ASME Code Class 1 Reactor Coolant Pressure Boundary, Process, Drain, Test, and Flush Lines and Connections."
- 2. Entergy letter NL-05-118 to NRC, dated October 27, 2005; regarding reply to NRC RAI for subject Relief Request.
Dear Sir:
Entergy Nuclear Operations, Inc (Entergy) is submitting additional information to support NRC review of an Inservice Inspection Program relief request submitted in Reference 1. Entergy previously submitted additional information in Reference 2 and during a followup telecom with NRC staff, the need for further clarification was identified. The requested information is provided in the Attachments to this letter.
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NL-05-1 35 Docket 50-247 Page 2 of 2 There are no new commitments identified in this submittal. If you have any questions or require additional information, please contact Mr. Patric W. Conroy, Licensing Manager at (914) 734-6668.
Ve truly yours, a icW. Conroy Licensing Manager Indian Point Energy Center cc: Mr. John P. Boska, Senior Project Manager, NRC NRR Mr. Samuel J. Collins, Regional Administrator, NRC Region 1 NRC Resident Inspectors Office, Indian Point Unit 2 Mr. Peter R. Smith, NYSERDA Mr. Paul Eddy, NYS Department of Public Service
ATTACHMENT 1 TO NL-05-135 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING INDIAN POINT 2 ISI RELIEF REQUEST RR-74 ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247
Attachment 1 to NL-05-135 Docket 50-247 Page 1 of 5 The following clarifications requested by NRC were discussed during a conference call with Entergy personnel on November 15, 2005 and pertain to information submitted in Entergy letter NL-05-1 18 dated October 27, 2005.
NRC QUESTION:
Provide additional information regarding the hardship of complying with the hydrostatic pressure test requirements for the pipe segments described in line items 10 through 18 of the Attachment 2 Table in Entergy letter dated October 27, 2005.
These pipe segments are part of the Residual Heat Removal or Safety Injection systems and may be subject to alternate test pressures as previously approved by the NRC staff in ML050810464. Determine if the system design at Indian Point 2 supports the implementation of similar alternate test pressures.
ENTERGY RESPONSE:
Entergy is providing a revision of the previously submitted Pipe Segment Data Table to incorporate responses to the NRC followup questions regarding hardship and alternate test pressure for the pipe segments described by line items 10 through 18 in the Table.
The additional hardship information for line items 11 through 18 reflects the personnel safety and spill considerations associated with the use of temporary jumper hoses to bypass check valves. The additional hardship information for line item 10 reflects the need to bypass the pressure interlock in the control circuit for valve 731.
The table is also updated to document the proposed test pressure that Entergy has agreed to incorporate in this relief request. The RHR pipe segments in line items 10, 12, and 14 will be inspected at a pressure of at least 350 psig. The SI pipe segments in line items 11, 13, and 15 through 18 will be inspected at a pressure of at least 1450 psig. These inspections will meet the current VT-2 visual examination hold-time limits of 10 minutes for non-insulated components and 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for insulated components. It is reasonable to expect that the proposed test pressures and examination hold times will be sufficient to produce detectable leakage from significant service-induced degradation sources, if they exist, which satisfies the intent of the pressure test.
Attachment I to NL-05-135 Docket 50-247 Page 2 of 5 IP2 ISI RELIEF REQUEST RR-74 PIPE SEGMENT DATA NOTE: THIS TABLE SUPERSEDES AND REPLACES THE ATTACHMENT 2 TABLE OF NL-05-118 i17
- A%IIIu Iul.JIc4 - U~da leg r VI IE I UPv HOWe is [equesed hrom Heat Exhanger 3" Dia Type psig remains Isolated in 2000. No cycling valve 4970 in order flush taps. 316 indication. to pressurize downstream pipe piece and blank.
1 Regenerative SCH 160 #27 A 376 2580 NONE NONE - dead leg PT on 27-12AA 206685 <1 ft 0.33 mr Relief is requested from Heat Exhanger 3" Dia Type psig remains isolated in 2000. No cycling valve 4972 in order flush taps. 316 indication. to pressurize downstream 2 pipe piece and blank.
Regenerative SCH 160 # 80 A 376 2580 NONE NONE - dead leg PT on 80-1AA 206714 <1 ft 575 mr Relief is requested from Heat Exhanger 3" Dia Type psig remains isolated in 1997. No cycling valve 4978 in order flush taps. 316 indication. to pressurize downstream 3 pipe piece and blank.
Regenerative SCH 160 # 64 A 376 2580 NONE NONE - dead leg No inspection 206711 c 1 ft 67 mr Relief is requested from Heat Exhanger 3" Dia Type psig remains isolated performed cycling valve 4974 in order flush taps. 316 to pressurize downstream 4 _pipe piece and blank.
Regenerative SCH 160 # 79 A 376 2580 NONE NONE - dead leg 206713 <1 ft 575 mr Relief is requested from Heat Exhanger 3" Dia Type psig remains isolated No inspection cycling valve 4976 in order flush taps. 316 performed to pressurize downstream 5 pipe piece and blank.
Reactor SCH 160 # 81 A 376 2580 NONE NONE - dead leg PT on 81-6, 206715 1 ft 13 mr Relief is requested from Coolant 2" Dia Type psig remains isolated 81-7, 81-8 in cycling valve 508A in order System loop 316 1997. No to pressurize downstream drain lines. indication. pipe piece and valves 508B 6 and 542.
Reactor SCH 160 #82 A 376 2580 NONE NONE - dead leg No inspection 206716 1 ft 13 mr Relief is requested from Coolant 2" Dia Type psig remains isolated performed cycling valve 505A in order System loop 316 to pressurize downstream 7 drain lines. pipe piece and valve 505B.
Reactor SCH 160 #83 A 376 2580 NONE NONE - dead leg No inspection 206717 1 ft 13 mr Relief is requested from Coolant 2" Dia Type psig remains isolated performed cycling valve 51 1A in order System loop 316 to pressurize downstream 8 drain danlnslines. pipe piece and valve 511 B.
Attachment 1to NL-05-135 Docket 50-247 Page 3 of 5 IP2 ISI RELIEF REQUEST RR-74 PIPE SEGMENT DATA
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- A-- TUC ATTAl- 3* AC rmeauur own 1E ,. 9tu r VU remains - uiatdU r a upI mu-r1al Reliet is requested trom Coolant 2" Dia Type psig remains isolated 2000. No cycling valve 515A in order System loop 316 indication.: to pressurize downstream 9 drain lines. pipe piece and valve 515B.
Residual Heat SCH 140 # 10 A 376 2580 > 350 psig 700 psig 1400 UT and PT on 206669 75 ft < 1.0 mr Relief is requested from Removal Line 14m Dia Type psig deg F. Taken 10-17. 10-18 in cycling valve 731 in order to from the 316 from 1P2 UFSAR 2000. No pressurize downstream Reactor 6.2.2.3.13 Piping indication. pipe piece and valve 730.
Coolant as a Design Valve interlocks prevent System. Parameter for valve opening above 365 RHR. Transient psig RCS pressure.
conditions will not exceed these 10 values.
Safety Injection SCH 140 # 351 A 376 2580 > 1450 1500 psig /300 PT on 56-91 in 206903 28 ft <1.0 mr Relief is requested from and Residual 10" Dia # 355 Type psig psig deg F. Taken 1997. No 206906 and installing and removing Heat Removal SCH 160 # 56 316 from IP2 UFSAR indication. 206700 2 ft temporary jumper hoses Lines to the 6" Dia 6.2.2.3.13 Piping and from downstream of 897A Reactor SCH 160 as a Design 1 ft check valve to pressurize Coolant 2" Dia Parameter for SI. upstream piping due to System. The transient increased risk of coolant conditions will not spill and personnel hazard exceed these at high pressure and 11 values. temperature.
Safety Injection SCH 140 # 352 A 376 2580 > 350 psig 700 psig / 400 No inspection 206904 12 ft < 1.0 mr Relief is requested from and Residual 10" Dia # 356 Type psig deg F. Taken performed 206907 and installing and removing Heat Removal SCH 160 316 from IP2 UFSAR <1 ft temporary jumper hoses Lines to the 6* Dia 6.2.2.3.13 Piping from downstream of 897B Reactor as a Design check valve to pressurize Coolant Parameter for upstream piping due to System. RHR. Transient increased risk of coolant conditions will not spill and personnel hazard exceed these at high pressure and 12 l values. temperature.
Attachment 1 to NL-05-135 Docket 50-247 Page 4 of 5 IP2 ISI RELIEF REQUEST RR-74 PIPE SEGMENT DATA Q:IOPOQrnCC AwMn D13I AP1=C T4IF ATTA(%RA1NIT 7 TA Satety Injection SCH 140 #353 A 376 > 14~ I1u5 psig ;3uu UT ando-I on ou It Kellel Is requescu 1uuTr and Residual 10" Dia # 358 Type psig psig deg F. Taken 353-6 in 1995. 206908 and installing and removing Heat Removal SCH 160 #56 316 from IP2 UFSAR Root geometry 206701 12ft temporary jumper hoses Lines to the 6" Dia 6.2.2.3.13 Piping found and and from downstream of 897C Reactor SCH 160 as a Design accepted on 3ft check valve to pressurize Coolant 2" Dia Parameter for Si. the UT. Minor upstream piping due to System. The transient indication increased risk of coolant conditions will not found and spill and personnel hazard exceed these accepted at high pressure and 13 values durina PT. temperature.
Safety Injection SCH 140 # 350 A 376 2580 > 350 psig 700 psig /400 No inspection 206901 18 ft < 1.0 mr Relief is requested from and Residual 10" Dia # 361 Type psig deg F. Taken performed 206910 and installing and removing Heat Removal SCH 160 316 from IP2 UFSAR <1 ft temporary jumper hoses Lines to the 6" Dia 6.2.2.3.13 Piping from downstream of 897D Reactor as a Design check valve to pressurize Coolant Parameter for upstream piping due to System. RHR. The increased risk of coolant transient spill and personnel hazard conditions will not at high pressure and exceed these temperature.
14 values.
Safety Injection SCH 160 # 16 A 376 2580 > 1450 1500 psig /300 PT on 16- 206683 87 ft < 1.0 mr Relief is requested from Lines to the 2" Dia Type psig psig deg F. Taken 48,16-49,16- installing and removing Reactor 316 from IP2 UFSAR 50,16-51,16- temporary jumper hoses Coolant 6.2.2.3.13 Piping 51A in 1997. from downstream of 857A System. as a Design No indication. check valve to pressurize Parameter for Si. upstream piping due to The transient increased risk of coolant conditions will not spill and personnel hazard exceed these at high pressure and 15 values. temperature.
/
Attachment I to NL-05-135 Docket 50-247 Page 5 of 5 IP2 [SI RELIEF REQUEST RR-74 PIPE SEGMENT DATA
- I IOCOERr e= AWN DOMI AIC.. TrUC ATTAf1iA=KIT'9 T afety injec A WC >14 1 00 psig 1300 PT on 56- < 1.0 mr Relief is requested from Lines to the 2" Dia Type psig psig deg F.Taken 10,56-11,56- installing and removing Reactor 316 from IP2 UFSAR 12,56-13,56- temporary jumper hoses Coolant 6.2.2.3.13 Piping 22,56-23,56- from downstream of 857B System. as a Design 24,56-24.1,56- check valve to pressurize Parameter for SI. 24.2,56-25,56- upstream piping due to The transient 26 in 1997. increased risk of coolant conditions will not Minor spill and personnel hazard exceed these indication at high pressure and values. found and temperature.
accepted on 56-24.2.
Safety Injection SCH 160 # 16 A 376 2580 > 1450 1500 psig / 300 No inspection 206682 37 ft <1.0 mr Relief is requested from Lines to the 2" Dia Type psig psig deg F. Taken performed installing and removing Reactor 316 from IP2 UFSAR temporary jumper hoses Coolant 6.2.2.3.13 Piping from downstream of 857C System. as a Design check valve to pressurize Parameter for Si. upstream piping due to The transient increased risk of coolant conditions will not spill and personnel hazard exceed these at high pressure and 17 values. temperature.
Safety Injection SCH 160 # 16 A 376 2580 > 1450 1500 psig / 300 No inspection 206683 15 ft <1.0 mr Relief is requested from Lines to the 2" Dia Type psig psig deg F. Taken performed installing and removing Reactor 316 from IP2 UFSAR temporary jumper hoses Coolant 6.2.2.3.13 Piping from downstream of 857D System. as a Design check valve to pressurize Parameter for Si. upstream piping due to The transient increased risk of coolant conditions will not spill and personnel hazard exceed these at high pressure and 18 values. temperature.