NL-05-118, Reply to RAI Regarding Request for Relief from System Hydrostatic Test Requirements for Large Bore Pipe IP2-RR-74
| ML053080244 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 10/27/2005 |
| From: | Conroy P Entergy Nuclear Northeast |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-05-118, TAC MC7307 | |
| Download: ML053080244 (35) | |
Text
-Entergy Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel 914-734-6668 Patric Conroy Licensing Manager Indian Point Energy Center October 27, 2005 Re:
Indian Point Unit 2 Docket No. 50-247 NL-05-118 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
References:
Reply to RAI regarding Request for Relief From System Hydrostatic Test Requirements for Large Bore Pipe IP2-RR-74 (TAC MC7307)
- 1. NRC letter dated September 29, 2005; Request for Additional Information Regarding Request for Relief From System Hydrostatic Test Requirements for Large Bore Pipe (TAC MC7307)".
- 2. Entergy letter to NRC (NL-05-073) 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 (RCPB), Process, Drain, Test, and Flush Lines and Connections".
Dear Sir; Entergy Nuclear Operations, Inc. is providing a response to the NRC request for additional information in Reference 1 regarding the Request for Relief From System Hydrostatic Test Requirements for Large Bore Pipe (Reference 2) for Indian Point 2 (1P2). The responses to questions are provided in Attachment 1.
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.
Patric W. Conroy Licensing Manager Indian Point Energy Center 1- I
NL-05-1 18 Docket 50-247 Page 2 of 2 : Reply To NRC, "Request For Additional Information Regarding Request For Relief From System Hydrostatic Test Requirements For Large Bore Pipe (TAC MC7307)". : Relief Request #74 Pipe Segment Data : Relief Request #74 Isometric Drawings cc:
Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission Resident Inspector's Office Indian Point Unit 2 U.S. Nuclear Regulatory Commission Mr. John P. Boska, Sr. Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mr. Peter R. Smith, President NYSERDA Mr. Paul Eddy New York State Department of Public Service TO NL-05-118 REPLY TO NRC, -REQUEST FOR ADDITIONAL INFORMATION REGARDING REQUEST FOR RELIEF FROM SYSTEM HYDROSTATIC TEST REQUIREMENTS FOR LARGE BORE PIPE (TAC MC7307)".
ENTERGY NUCLEAR OPERATIONS, INC INDIAN POINT NUCLEAR GENERATING UNIT 2 DOCKET 50-247
NL-05-118 Docket 50-247 Attachment I Page 1 of 4 Request for Additional Information NRC letter dated September 29, 2005 (TAC NO. M7307)
The following responses are provided based on Nuclear Regulatory Commission (NRC) staff questions from the submittal review:
- 1. Please confirm the start and end dates for the third 10-year in-service inspection (ISI) interval at IP2.
Response: IP2 third 10-year interval started on July 1,1994 and will end on December 31, 2006. The interval has been extended due to outages greater than six months and to coincide with a refueling outage as allowed by the 1989 Edition of the ASME Boiler and Pressure Vessel Code paragraph IWA-2430(e) and IWA-2430(d) respectively.
- 2. Requirements for pressure testing found in both the ASME Code and ASME Code Case N-498-4 were cited in Relief Request (RR) RR-74. ASME Code Case N-498-4 is an alternative to certain ASME Code requirements for hydrostatic pressure testing of ASME Class 1, 2, and 3 components, and is approved in Revision 13 of Regulatory Guide (RG) 1.147, 'In-service Inspection Code Case Acceptability, ASME Section Xl, Division I,' for general use, provided the licensee meets the stated condition that hold times during these pressure tests are maintained according to the 1989 Edition of ASME Code, Section Xl. The licensee's proposal contains references to both ASME Code and ASME Code Case N-498-4 requirements, therefore, it appears the licensee has adopted the alternatives described in the ASME Code Case N-498-4 (with the condition imposed), in conjunction with associated ASME Code requirements that are required for pressure testing of the subject components.
Please note that ASME Code Case N-498-4 is a voluntary alternative to ASME Code requirements and the staff expects that ASME Code Cases approved in RG 1. 147 will be adopted in their entirety. Further, Title 10 of the Code of Federal Regulations (10 CFR),
Section 50.55a(a)(3), allows licensees to propose alternatives to ASME Code requirements, provided (i) an acceptable level of quality and safety will be realized by the alternative, or (ii) existing ASME Code or CFR requirements would impose an unusual hardship or difficulty without a compensating increase in quality and safety. However, no mechanism for evaluating a licensee's proposal to an existing, NRC approved, voluntary alternative, is allowed by the provisions at 10 CFR 50.55a(a)(3). This would, in effect, be providing an alternative to an alternative.
The issue related to test pressures and temperatures for the piping segments defined in RR-74 should be addressed as a stand alone alternative to ASME Code requirements, not as an alternative to ASME Code Case N-498-4. Please revise the proposal accordingly, re-state the basis for the alternative, describe the hardship or unusual difficulty that would be incurred if the ASME Code or CFR requirements are imposed, and clearly define all conditions or provisions that will be met by the proposed alternative.
NL-05-118 Docket 50-247 Page 2 of 4 Response: Entergy is proposing to use a "system leakage test" described in IWB-5221 in lieu of the "system hydrostatic test" described in IWB-5222 that is required at the end of the 10-year interval. Code Case N-498-4 was inadvertently cited in the original relief request submittal, under Section 5.0, "Proposed Alternative", 3d paragraph, "Small Size Class I System Drain, Test and Flush Lines". It is proposed that the words "Code Case N-498-4" be replaced with "proposed" in the same paragraph. The following paragraph is a reprint of the complete paragraph as proposed:
Small Size Class I System Drain, Test and Flush Lines Relief is requested from fully pressurizing piping between the first and second isolation device. There are nine lines of 2-inch or 3-inch diameter listed in Attachment I for use as drains, test and flush lines. The configurations are two isolation valves in series or a valve and a blind flange. In some configurations, the piping segment may tee to additional lines where an additional valve, cap or flange provides the second boundary. The piping segments provide the design required double isolation barrier for the reactor coolant pressure boundary. The proposed system leakage test would be performed at pressure associated with 100% reactor power where temperature shall not exceed the limiting temperature for the corresponding pressure (IWB-5230(a)). Pressure testing of these piping segments at nominal operating pressure would require the opening of the inboard isolation valve at normal operating RCS pressure conditions. Opening the inboard isolation valve is contrary to the design double-barrier requirement and introduces potential risk for spills and personnel contamination. Opening of the inboard valve introduces the possibility of a personnel safety hazard if a flange fails in the presence of inspection personnel.
- 3. For each of the piping segments listed in the table in the proposed alternative, please provide the piping material, piping design pressure and proposed test pressure. In addition, submit the isometric drawings associated with the piping segments.
Response: The piping material, piping design pressure and proposed test pressure are given for the pipe segments listed in Attachment 2. As stated in the relief request there is no alternate test pressure since the pressure-side isolation will not be opened or bypassed. All the referenced isometric drawings for the relevant piping are provided in.
- 4. For the piping segments discussed in RR-74, list any other examinations that are conducted to ensure structural or leakage integrity. Specifically, describe any volumetric or surface examinations being performed as part of the current ISI program, and list any indications that have resulted from these examinations.
Response: The examinations and any indications are listed in Attachment 2.
NL-05-1 18 Docket 50-247 Page 3 of 4
- 5. State the operating pressures and temperatures of these piping segments during a plant event that requires safety injection, (i.e., operation of the lines). Include a discussion regarding why the proposed pressure and temperature is adequate to ensure leakage integrity for these lines.
Response: There are no proposed pressures or temperatures since the pressure-side isolation valve will not be opened or bypassed. The drain valves will not be operated in a safety injection transient. The residual heat removal and safety injection segments will be subject to pressures and temperatures less than the design pressure and temperature of the respective supply systems. The information for each segment is provided in.
- 6. In Section 6 of RR-74, "Basis for Relief Request," it is stated that there would be additional radiation exposure to plant personnel if the ASME Code system leakage test was performed to the full system boundary, but an estimated radiation dose to plant personnel was not provided. For each item in attachment 1 of your submittal, please provide the estimated dose savings which would result if this relief was approved.
Response: The estimated dose savings is provided for each segment in Attachment 2.
ATTACHMENT 2 TO NL-05-1 18 RELIEF REQUEST #74 PIPE SEGMENT DATA (4 PAGES)
ENTERGY NUCLEAR OPERATIONS, INC INDIAN POINT NUCLEAR GENERATING UNIT 2 DOCKET 50-247
NL-05-118 Attachment 2 IP#2 RELIEF REQUEST#74 PIPE SEGMENT DATA I -
.
3roeinsemet Dose SavIngs Reauest or Regenerative Heat Exhanger flush taps.
3" Dia A 376 Type 316 psig NIUNt - dead leg remains isolated PIT on 1 9-2000. No indication.
2.82 mr Relief is requested from cycling valve 4970 in order to pressurize downstream pipe piece and blank.
1 Regenerative SCH 160
<1 ft 0.33 mr Relief is requested from Heat Exhanger 3" Dia Type psig remains isolated 2000. No cycling valve 4972 in flush taps.
316 indication.
order to pressurize downstream pipe piece 2
_a n d b la n k.
Regenerative SCH 160
< 1 ft 575 mr Relief is requested from Heat Exhanger 3" Dia Type psig remains isolated 1997. No cycling valve 4978 in flush taps.
316 indication.
order to pressurize downstream pipe piece 3
and blank.
Regenerative SCH 160
- 64 A 376 2580 NONE NONE - dead leg No inspection 206711
< 1 ft 67 mr Relief is requested from Heat Exhanger 3" Dia Type psig remains isolated performed cycling valve 4974 in flush taps.
316 order to pressurize downstream pipe piece 4
_a n d b la n k.
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 flush taps.
316 performed order to pressurize downstream pipe piece
_and blank.
Reactor SCH 160
- 81 A 376 2580 NONE NONE - dead leg PT on 81-6, 81-7, 206715 1 ft 13 mr Relief is requested from Coolant 2" Dia Type psig remains isolated 81-8 in 1997. No cycling valve 508A in System loop 316 indication.
order to pressurize drain lines.
downstream pipe piece and valves 508B and 6
_5 4 2.
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 System loop 316 order to pressurize drain lines.
downstream pipe piece 7
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, and valve 505B.
Page 1 of 4
NL-05-118 Attachment 2
_e th! esavings equest Coolant System loop drain lines.
2" Dia r% 31V Type 316 zuou psig P4ulmr4 - ueau lug remains isolated perforned 206717 1 f 13 mr Relief is requested from cycling valve 511A in order to pressurize downstream pipe piece and valve 511 B.
8 Reactor SCH 160
- 84 A 376 2580 NONE NONE - dead leg PT on 84-6 in 206718 1 ft 13 mr Relief is requested from Coolant 2" Dia Type psig remains isolated 2000. No cycling valve 515A in System loop 316 indication.
order to pressurize drain lines.
downstream pipe piece 9
and valve 515B.
Residual Heat SCH 140
- 10 A 376 2580 NONE 700 psig /400 deg UT and PT on 10-206669 75 ft NONE Relief is requested from Removal Line 14" Dia Type psig F. Taken from IP2 17,10-18 in 2000.
cycling valve 731 in from the 316 UFSAR 6.2.2.3.13 No indication.
order to pressurize Reactor Piping as a downstream pipe piece Coolant Design Parameter and valve 730.
System.
for RHR. The transient conditions will not exceed these 1 0 values.
Safety Injection SCH 140 A 376 2580 NONE 1500 psig /300 PT on 56-91 in 206903 28 ft NONE Relief is requested from and Residual 10" Dia 351 Type psig deg F. Taken 1997. No 206906 and installing and removing Heat Removal SCH 160 316 from IP2 UFSAR indication.
206700 2 ft temporary jumper hoses Lines to the 6" Dia 355 6.2.2.3.13 Piping and from downstream of Reactor SCH 160
- 56 as a Design 1 ft 897A check valve to Coolant 2" Dia Parameter for SI.
pressurize upstream System.
The transient piping.
conditions will not exceed these 11
_values.
Safety Injection SCH 140 A 376 2580 NONE 700 psig /400 deg No inspection 206904 12 ft NONE Relief is requested from and Residual 10" Dia 352 Type psig F. Taken from IP2 performed 206907 and installing and removing Heat Removal SCH 160 316 UFSAR 6.2.2.3.13
< 1 ft temporary jumper hoses Lines to the 6" Dia 356 Piping as a from downstream of Reactor Design Parameter 897B check valve to Coolant for RHR. The pressurize upstream System.
transient piping.
conditions will not 12 exceed these Page 2 of 4
NL-05-118 Attachment 2 0RFt~l IF.Q74t7A PIPF.RFr in--ll Pw
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19
R.equest Safety Injection SCH 140 A 376 2580 NONE 1500 psig /300 UT and PT on 206905 10ft NONE Relief is requested from and Residual 10" Dia 353 Type psig deg F. Taken 353-6 in 1995.
206908 and installing and removing Heat Removal SCH 160 316 from IP2 UFSAR Root geometry 206701 12 ft temporary jumper hoses Lines to the 6" Dia 358 6.2.2.3.13 Piping found and and from downstream of Reactor SCH 160
- 56 as a Design accepted on the 3 ft 897C check valve to Coolant 2" Dia Parameter for SI.
UT. Minor pressurize upstream System.
The transient indication found piping.
conditions will not and accepted exceed these during PT.
1 3 values.
Safety Injection SCH 140 A 376 2580 NONE 700 psig /400 deg No inspection 206901 18 ft NONE Relief is requested from and Residual 10" Dia 350 Type psig F. Taken from IP2 performed 206910 and installing and removing Heat Removal SCH 160 316 UFSAR 6.2.2.3.13
< 1 ft temporary jumper hoses Lines to the 6" Dia 361 Piping as a from downstream of Reactor Design Parameter 897D check valve to Coolant for RHR. The pressurize upstream System.
transient piping.
conditions will not exceed these 14 values.
Safety Injection SCH 160
- 16 A 376 2580 NONE 1500 psig /300 PT on 16-48,16-206683 87 ft NONE Relief is requested from Lines to the 2" Dia Type psig deg F. Taken from 49,16-50,16-installing and removing Reactor 316 IP2 UFSAR 51,16-51A in temporary jumper hoses Coolant 6.2.2.3.13 Piping 1997. No from downstream of System.
as a Design indication.
857A check valve to Parameter for SI.
pressurize upstream The transient piping.
conditions will not exceed these 1 5 values.
Page 3 of 4
NL-05-118 Attachment 2 Dcool 110T1t7A PIP; QEV avfig Bequest Satety injection Lines to the Reactor Coolant System.
SMH 1i 2" Dia A 376 Type 316 psig deg F. Taken from IP2 UFSAR 6.2.2.3.13 Piping as a Design Parameter for SI.
The transient conditions will not exceed these values.
PI on 56-1U,56-11,56-12,56-13,56-22,56-23,56-24,56-24.1,56-24.2,56-25,56-26 in 1997.
Minor indication found and accepted on 56-24.2.
61 ft NONE Relief is requested from installing and removing temporary jumper hoses from downstream of 857B check valve to pressurize upstream piping.
16 Safety Injection SCH 160
- 16 A 376 2580 NONE 1500 psig /300 No inspection 206682 37 ft NONE Relief is requested from Lines to the 2" Dia Type 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 System.
as a Design 857C check valve to Parameter for SI.
pressurize upstream The transient piping.
conditions will not exceed these 17 values.
Safety Injection SCH 160
- 16 A 376 2580 NONE 1500 psig /300 No inspection 206683 15 ft NONE Relief is requested from Lines to the 2" Dia Type 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 System.
as a Design 857D check valve to Parameter for SI.
pressurize upstream The transient piping.
conditions will not exceed these 18 values.
Page 4 of 4
ATTACHMENT 3 TO NL-05-118 RELIEF REQUEST #74 ISOMETRIC DRAWINGS (23 PAGES)
Drawing Page (x of 23)
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