ML20153F615
| ML20153F615 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 09/21/1998 |
| From: | Swailes J NEBRASKA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLS980145, NUDOCS 9809290178 | |
| Download: ML20153F615 (24) | |
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4 COOPER NUCLEAR STATION P.O. BOX 98. BROWNVILLE. NEBRASKA $8321 TELEPHONE (402)t25-3011 Nebraska Public Power District =<===
NLS980145 September 21,1998 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 Gentlemen:
Subject:
Inservice inspection Relief Requests Cooper Nuclear Station, NRC Docket 50-298, DPR-46
Reference:
- 1. Letter (No. NLS980020) to USNRC Document Control Desk from G. R. Ilorn (NPPD) dated April 23,1998, " Cooper Nuclear Station Inservice Inspection ReliefRequests"
- 2. Letter to G. R. Ilorn (NPPD) from D. L. Wigginton for J. R. IIall (USNRC) dated August 14,1998," Request for Additional Information Regarding Cooper Nuclear Station Third Interval Inservice Inspection Program Plan Requests for Relief (TAC No. MA2138)"
In April 1998, Nebraska Public Power District (District ) submitted two revised and one new relief request for the Inservice Inspection Program (Reference 1). The NRC requested additional information (Reference 2) on certain of these relief requests. The attachments to this letter provide the additional information requested.
Should you have any questions concerning this matter, please contact me.
Since ly, ,
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John 11. wailes Vice President of Nuclear Energy
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9809290178 980921 "
PDR ADOCK 05000298 !
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. NLS980145_ '
September 21,1998 Page 2 of 2' cc: Regional Administrator USNRC - Region IV
- j. Senior Project Manager
,. USNRC - NRR Project Directorate IV-1 l l
l Senior Resident inspector )
USNRC '
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( MichaelT. Anderson INEEL Research Center
, NPG Distribution I
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l Attachment 1 to NLS980145 l' age 1 of 4 i Response to Request for AdditionalInformation
, Cooper Nuclear Station Inservice Inspection Program I Relief Requests i
Attachment 1 !
- a. Requestfor ReliefRI-17, Revision 1. The Licensee is proposing an alternative to the minimum examination requirements ofASME Code Case N-509for several Class 1 piping i integral attachment svelds. In an SER dated October 23, I997, the Licensee tras authori:ed i to use Code Case N-509 and committed to perform a minimum 10% examination ofall Class I, 2, and 3 piping, pump and valve integral attachment welds.
Code Case N-509 sigmficantly reduces the number ofexaminations (from 100 to 10%)
required during each interval; this is consistent with the sampling philosophy used by the Codefbr other Examination Categories. However, no guidcmce is givenfor which components are to be examined: therefore, the licensee may use a certain level ofdiscretion when choosing examination items.
Do additional integrally welded attachments, not currently being examined, exist within the same Class I systems as thosefor which reliefis being requested?
Response. Yes. Additional integrally welded attachments, not currently being examined, do exist in most of the systems for which reliefis being requested.
Are there other welds that could be examined to provide the minimum required to meet Code Case N-509?
Response. No. No other welds could reasonablely be selected for the integral attachments identified in the relief request. Code Case N-509 implies that the integral attachments selected for examination should be associated with the supports selected for examination under IWF. (Copper Nuclear Station uses Code Case N-491 for the selection and examination of component supports.) In addition, the selected supports and integral attachment welds should be distributed throughout the piping systems in order to provide a representative sample. This was the basis CNS used for selecting the integral attachments to be examined. Details for each of the affected systems are as follows:
There me 17 integral attachments on the Class 1 Feedwater piping. The Class 1 Feedwater system consists of four loops of piping from each of the Feedwater nozzles, which merge into two main loops before exiting the primary containment.
One integral attachment on Loop A and one integral attachment on loop 13 were selected for examination. The other integral attachments in the Feedwater system also have access restrictions or were previously excluded from examination. Some of the pipe clamps associated with these integral attachments were installed by welding and can not easily be disassembled. The accessible portions of an additional integral attachment weld on the Feedwater system will be examined to compensate for the restricted access.
Attachment I to NLS980145 Page 2 of 4
.There are only 2 integral attachments on the Recirculation system piping (the other integral attachments are on the pumps). Both of the attachments are similar in design but are on different piping loops. The integral attachment on loop A was selected for examination. The accessible portions of the integral attachment on loop B will also be examined to compensate fbr the restricted access on the loop A attachment.
The attachment on the Scram Discharge Piping is the only integral attachment weld in the non-exempt portion of this system. Thus there is no other integral attachment weld to be selected.
There are 94 integral attachments on the Residual I! cat Removal piping (the other integral attachments are on the pumps and the heat exchangers). Ten of the pipe integral attachments were selected for examination to meet the 10% sample requirements. The ten attachments consist of fbur hanger lugs, three elbow lugs, and three stanchions. RilA-CEl-2 was selected because it was previously examined in the second interval and has a high design load. The accessible portions of another similar integral attachment in the RIIR system will be examined to compensate fbr the restricted access on the RilA-CEl-2.
Please providefurther information, including lists of.; 1) the total number ofattachment welds in all Class I piping systems; 2) the number scheduledfor examination during the interval; and 3) the estimatedpercentage of the totalpojndation obstructed by clamps, restraints. or other appurtenances.
Response.1) The Inservice Inspection (ISI) Program provides lists of the Class I and 2 non-exempt attachment welds in each system by Code item number and identities the specific integral attachments selected fbr examination each period. l'or your convenience this infbrmation is also provided as Attachment 2. There are 72 Class I pipe integral attachments and 147 Class 2 pipe integral attachments.
- 2) There are 13 Class 1 pipe integral attachments scheduled for inspection during the interval. There are 20 Class 2 pipe integral attachments scheduled for inspection during the interval.
l 3) In lieu of providing an estimate of the total population ofintegrally welded l attachments which are in some way obstructed, the District proposes
- inspecting the accessible portions of additional integral attachments in the affected systems as stated above.
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Attachment I to NLS980145 Page 3 of'4 l
l h. Requestfor Relief RI-25, Revision O. The licensee is requesting reliell hased on
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impracticality,for the VT-1 Visual Examinations requiredfor integral attachment welds on Class 3 Service IVater Pumps. In an SER dated October 23,1997, the Licensee was authori:ed to use Code Case N-509 and committed to perform a mininnun 10% examination j ofall Class 1, 2, and 3 piping, pump and valve integral attachment welds. Additional i
guidancefor selection ofthese welds is listed in Table 2500-1 ofthe Code Case.
The licensee stated:
"There arefour vertical service waterpumps. Each SWpump has an interior and exterior l fillet weld attaching the pump discharge head to the pump column and afillet weld attaching the pump column to the mounting plate. The portions of these welded attachments inside the discharge head are partially inaccessible due to the limited access through the service port in the discharge head and the configuration of the pump cohann.
l A complete examination is not possible. Approximately 60% of the total weld length is accessiblefor examination.
As an alternate examination, CNS willperform a visual examination (VT-1) of the accessible portions of welded attachments on two SWpumps. This is a 50% sample of the welded attachments of the SWpump component supports. "
l Code Case N-509 requires that the attachments selectedfor examination be only those on l
the outside surface of the pressure-retaining component. Additionally, the Code Case requires that only 10% ofthe applicable welds be examined, within other restrictions. Based on these requirements, it is unclear whether reliefis necessary. Please discuss these l discrepancies and, llreliefis still necessary, provide drawings ofthe Service Water Pumps, i
depicting location and access restrictionsfor the integrally welded attachments.
Response. There are four Service Water Pumps. The integral attachment welds on one pump need to be examined to meet the requirements of Code Case N-509. The Service Water Pump discharge head is located inside a pump support cylinder which is welded to a base plate. The top of the pump support cylinder is the support for the pump motor. The
' inlet of the discharge head is welded to the base plate and then connects to the pump column.
The outlet of the discharge head is welded to the pump support cylinder and then connects to the discharge piping. These welds are the integral attachments described in the relief request.
The attachments are on the exterior of the discharge head (i.e. the pressure retaining boundary), but inside and outside of the pump support cylinder. An access port in the pump support cylinder is provided for maintenance purposes and is the only access to the inside of t the pump support cylinder. Since the configuration of the pump support cylinder and c discharge head limits the access to the attachment welds inside the pump support cylinder, I
the requirements of N-509 can not be fully met. Thus this relief request is still required. In RI-25, CNS proposed examining the accessible portions of the integrally welded attachments on an additional Service Water pump as an alternative which would compensate for the restricted access to the welds on the single Service Water pump.
Attachment I to NLS980145 Page 4 of 4
'Attachinent 3 provides a Service Water pump configuration drawing that has been marked up to depict the location and access restrictions for the integral attachments.
Attachment 2 to NLS980145 14 Pages. Total
. l Attachment 2 l l
i Integrally Welded Attachments I (Sorted by ASME Class, System, and Item Number) l l
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CODE CASE N-509 COOPER NUCLEAR STATION IWB-2500-1 CAT: B-K-1 INSERVICE INSPECTION PROGRAM REV: 2 REACTOR FEEDWATER SYSTEM l
THIRD INTERVAL . <
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P I PE. . . . . . . . . . . . . . . . . . SYSTEM. . CNT . I TEM . NO. CF I G . . . . . . S I ZE . . TKNS . . . . . MAT . . . . 1 S0. . . . . . . . . . . . . . . . . EXAMS . . . . . . . . . . . . . . . . . . . . PER RELREQ REMARKS I CWB-BK1-6 RF-A 1 810.20 STN CS 2509-1 MT/PT FWA-BK1-4 RF-A RFH-74... -
1 B10.20 HSL CS 2509-1' MT/PT RFH-72... (LUGS) MUST-REMOVE PIPE CLAMP ON !
SUPPORT RFN-72 TO ACCESS ,
COMPLETE EXAM AREA...
FWA-BK1-7 RF-A 1 . 810.20 SSL CS 2509-1 'MT/PT RFS-17...
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FWB-BK1-4 RF-A 1 B10.20 SSL CS 2509-1 MT/PT RFS-14...
FWA-BK1-12 RF-A 1 810.20 SSL CS 2509-1 MT/PT RFS-18,RFS-19... (12 FWA-BKi-16 RF-A 810.20 LUGS)...
1 SSL CS 2509-1 MT/PT FWA-BK1-28 RF-A B10.20 RFS-15... (LUGS) 1 HSL CS 2509-1 MT/PT RFH-69...
FWA-BK1-36 RF-A 1 810.20 SP-FM CS 2509-1 MT/PT RFH-68A... PLATE, ATTACHMENT WELDED TO CONT (
PEN X-9A, EXAM LIMITED DUE TO CONFIGURATION OF '
CONT PEN X-9A AND ATTACHMENT, RELIEF j' FWA BK1-80 REQUEST REQUIRED...
. RF-A 1 B10.20 SSL CS 2509-1 MT/PT RFS-16... MUST REMOVE I PIPE CLAMP TO ACCESS COMPLETE EXAM AREA, PIPE ,
CLAMP WELDED TOGETHER...
FWB-BK1-8 RF-A 1 810.20 HSL P2 2509-1 MT/PT 4
FWC-BK1-4 RF-8 810.20 1 RI-17 RFH-73... ;
1 HSL CS 2509-2 MT/PT RFH-66... (LUGS)
FWD-BK1-4 RF-B 1 810.20 HSL CS 2509-2 MT/PT FWD-BK1-7 RF-8 B10.20 HSL RFN-65... (LUGS) 1 CS 2509-2 MT/PT RFS-10... (LUGS)
FWD-BK1-12 RF-B 1 B10.20 SSL CS 2509-2 MT/PT RFS-8,RFS-9... (12 LUGS)...
FWD-BK1-26 RF-B 1 810.20 HSL CS 2509-2 MT/PT RFH-62... LUGS WELDED TO PIPE CLAMP ON SUPPORT RFH-62...
FWD-BK1-35 RF-B 1 B10.20 SP-FH CS 2509-2 MT/PT RFH-62A... PLATE.
ATTACHMENT WELDED TO CONT PEN X-98, EXAM LIMITED DUE TO CONFIGURATION OF .
CONT PEN X98 AND !
ATTACHMENT, RELIEF !
REQUEST REQUIRED... ;
FWC-BK1-8 RF-8 1 810.20 SSL CS 2509-2 MT/PT 2 RFS-13... '
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CODE CASE N-509 COOPER NUCLEAR STATION
'IWB-2500-1 CAT: B-K-1 INSERVICE INSPECTION PROGPAM REV: 2 .
MAIN STEAM SYSTEM THIRD INTERVAL .
- P I PE . . . . . . . . . . . . . . . . . . SYST EM . . CNT . I TEM . NO. CF I G. . . . . . S I ZE . . T KNS. . . . . MAT . . . . . ! $0. . . . . . . . . . . . . . . . . EXAMS . . . . . . . . . . . . . . . . . . . . PER RELREQ PEMARKS. . . . . . . . . . . .
PSA-8K1-23 MS 1 B10.20 SP-FH 'CS 2506-1 MT/PT MSH-134A... PLATE,.
ATTACHMENT WELDED TO CONT RSA-8K1*22 PEN X-11...
MS 1 810.20 IPS CS 2506-2 MT/PT MSH-149A...
RSA-BK1-23 MS 1 B10.20 STN CS 2506-2 MT/PT. MSM-150...
PSA-BK1-19 MS 1 B10.20 HSL CS 2506-1 MT/PT 1 .RI-17 MSH-134...
MSA-BK1-11 MS-A 1 810.20 SP CS GET31E611-4 MT/PT MS-SSA3...
MSA-BK1 13 MS-A 1 B10.20 SP CS GE731E611-4 MT/PT MS-SSA2...
MSA-BK1-18 MS-A 1 810.20 LUGS CS GE731E611-4 MT/PT MS-MA2...
MSA-BK1 28 MS-A 1 810.20 LUGS GE731E611-4 CS MT/PT HA-3...
MSA-BKS-44 MS-A 1 B10.20 SP-FH CS GE731E611-4 MT/PT MSH-167... ATTACHMENT I WELDED TO CONT PEN X-7A, EXAM LIMITED DUE To s CONFIGURATION OF CONT PEN X-7A AND ATTACHMENT, RELIEF REQUEST ,
REQUIRED...
MSA-BK1-GA1 MS-A 1 B10.20 HSL CS GE731E671 MT/PT MS-GA1...
MSA-BK1-6 MS-A 1 810.20 HSL CS GE731E611-4 MT/PT 3 MS-MA1... L
, MSB-BK1-5 MS-B 1 B10.20 HSL CS GE731E611-4 MT/PT MS-HB1... (LUGS)
GSB-BKS-11 MS-B 1 B10.20 SP CS GE731E611-4 MT/PT MS-SSB3...
MSB-BK1-12 MS-B 1 810.20 SP CS GE731E611-4 MT/PT MS-SSB2...
GSB-8KS-17 MS-B 1 810.20 LUGS CS GE731E611-4 MT/PT MS-H82...
MSB-BK1-40 MS-B 1 B10.20 SP-FH CS GE731E611-4 MT/PT MSH-168... ATTACHMENT s WELDED TO CONT PEN X-79, EXAM LIMITED DUE TO CONFIGURATION OF CONT PEN X-78 AND ATTACHMENT, .
RELIEF REQUEST I I
REQUIRED...
MSB-BKS-GB1 MS-B 1 B10.20 HSL CS GE731E671 MT/PT MS-GB1...
MSB-8K1-32 MS-B 1 810.20 LUGS CS GE731E611-4 MT/PT 2 MS-H83... i CSC-BK1-6 MS-C 1 B10.20 HSL CS GE731E611-4 MT/PT MS-HC1... (LUGS)
MSC-8K1-12 MS-C 1 B10.20 SP CS GE731E611-4 MT/PT MS-SSC3...
MSC-BKS-14 MS-C 1 B10.20 SP CS GE731E611-4 MT/PT MS-SSC2... >
MSC-BK1-15 MS-C 1 810.20 LUGS CS GE731E611-4 MT/PT MS-HC2... ;
QSC-8K1-20 MS-C 1 B10.20 LUGS CS GE731E611-4 MT/PT MS-HC3... -
QSC-BK9-23 MS-C 1 810.20 SP CS GE731E611-4 MT/PT MSH-169... ATTACHMENT WELDED TO CONT PEN X-7C, ,
EXAM LIMITED DUE To t
- CONFIGURATION OF CONT PEN X-7C AND ATTACHMENT, RELIEF REQUEST REQUIRED MSC-8K1-CC1 MS-C 1 B10.20 HSL CS GE731E671 MT/PT MS-GC1...
- 30 JAN 1998 PAGE 1
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9 CODE CASE N-509 COOPER NUCLEAR STATION
-IWB-2500-1 CAT: B-K-1 INSERVICE INSPECTION PROGRAM REV: 2 .
MAIN STEAM SYSTEM THIRD INTERVAL .
F I PE . . . . . . . . . . . . . . . . . . SYSTEM. . CNT . I TEM. NO. CF I G . . . . . . ' S I ZE . TKNS . . . . . MAT. . . . . I S0. . . . . . . . . . . . . . . . . EXAMS. . . . . . . . . . . . . . . . . . . . PER RELREQ REMARKS. . . . . . . . . . . .
MSD-BK1-6 MS-D 1 810.20 HSL CS GE731E611-4 MT/PT MS-MD1... (LUGS) MUST- ,.
REMOVE PIPE CLAMP ON SUPPORT MS-HD1 TO ACCESS COMPLETE EXAM AREA... l
~ MSD-BK1-11 MS-D 1 810.20 SP CS GE731E611-4 MT/PT MS- SSD3. . . l MSD-BK1-13 MS-D 1 810.20 SP CS GE731E611-4 MT/PT MS-SSD2...
MSD-BK1 18 MS-D 1 810.20 LUGS CS GE/31E611-4 MT/PT MS-MD2...
'ESD-BK1-48 MS-D 1 810.20 SP-FM CS GE731E611-4 MT/PT MSM-170... ATTACHMENT WELDED TO CONT PEN X-7D, EXAM LIMITRO DUE TO CONFIGURATION OF CONT PEN r
' X-7D AND ATTACHMENT, ;
RELIEF REQUEST i REDUIRED...
ESD-BK1-GD1 MS-D 1 810.20 HSL CS GE731E671 MT/PT MS-GD1...
MSD-BK1-32 MS-D 1 810.20 LUGS CS. ~GE731E611-4 MT/PT 3 MS-303...
MSDR-BK1-4A MSDR 1 810.20 STN .438 Pt 2506-3 MT/PT MSH-152...
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CODE CASE N-509 COOPER NUCLEAR STATION EWB-2500-1 CAT: B-K-1 INSERVICS INSPECTION PROGRAM REY: 2 RES!OUAL HEAT REMOVAL SYSTEM THIRD INTERVAL
- PI PE . . . . . . . . . . . . . . . . . . SYSTEM. . CNT . I TEM.NO. CF I G. . . . . . SIZE . . TKNS . . . . . MAT . . . . . ! S0. . . . . . . . . . . . . . . . . EXAMS. . . . . . . . . . . . . . . . . . . . PE R RELREQ REMARKS. . . . . . . . .
RNA-BK1-20 RHR 1 B10.20 HSL - CS 2510-1 MT/PT-RHA-BK1-24 RHR 1 B10.20 HSL CS 2510-1 RHH-34... (LUGS) '
- MT/PT RMS-69... (LUGS)
RHA-BK1-80 RHR 1 B10.20 HSL CS 2510-1 MT/PT RHA-BK1-81 RHH-33... (LUGS)
RHR 1 810.20 STN CS 2510-1 MT/PT RHS-70... '
RHB-BK1-9 RHR-A 1 B10.20 SSL CS 2510-4 MT/PT RHB-BK1-80 RHS-8... (LUGS)
RHR-A 1 B10.20 IPS CS 2410-4 MT/PT RHH-121...
f;HB-BK1-81 RHR-A 1 B10.20 IPS CS 2410-4 MT/PT RHH-123...
CHB-BK1-16 RHR-A 1 B10.20 SSL CS 2510-4 MT/PT 3 RMS-6... (LUGS)
RNC-BK1-13 RHR-B 1 810.20' SSL CS 2510-3 MT/PT RHS-15... (LUGS)
LHC-BK1-80 RHR-B 1 B10.20 SSL CS 2510-3 MT/PT RMS-18 AND RHS-19...
CHC-BK1-81 1- (LUGS)...
RHR-B B10.20 SSL CS 2510-3 MT/PT RHS-13... (LUGS)
RT.C-BK1-24 RHR-B 1 B10.20 STN CS 2510-3 MT/PT 1 RHH-70...
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CODE CASE N-509 COOPER NUCLEAR STATION 2 IWB-2500 1 CAT: B-K-1 INSERVICE INSPECTION PROGRAM REY: 2 .
- REACTOR RECIRCULATION SYSTEM THIRD INTERVAL . t P IPE . . . . . . . . . . . . . . . . . . SYSTEM. . CNT . I TEM.NO. CF I G. . . . . . S I ZE . . TKNS . . . . . MAT . . . . . I S0. . . . . . . . . . . . . . . . . EXAMS. . . . . . . . . . . . . . . . . . . . PER RELREQ REMARKS . . . . . . . . . . . . . . . . . .
RR-BK1-4A RR-A 1 B10.20 HSL SS ISO-RL-A PT 2 RR LDOP-A... LUGS FOR ,.
SUPPORT RR-H1-A...
RR-BK1-4B RR-B 1 810.20 HSL SS ' ISO-RL-B PT RR-H2-B... (LUGS) RR [
LOOP-8... ,
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i RR-BK1-1A RR-A 1 810.30 LUG SS 731E225 PT RR PMP-A... ATTACHMENT LUG FOR SUPPORTS RR-S$1-A :
AND RR-HS-A... [
RR-BK1-2A RR-A 1 810.30 LUG SS 731E225 PT RR PMP-A... ATTACHMENT !
LUG FOR SUPPORTS RR-SS2-A L AND RR-H7-A...
RR-BK1-3A RR-A 1 810.30 LUG SS 731E225 PT RR PMP-A... ATTACHMENT LUG FOR SUPPORTS RR-SSS-A AND RR-H6-A...
RR-8K1-18 RR-B 1 810.30 LUG SS 731E225 PT 3 RR PMP-8... ATTACHMENT LUG FOR SUPPORTS RR-SSI-B i
' AND RR-MS-B...
fir-BK1 -28 RR-B 1 810.30 LUG SS 731E225 PT 3 RR PMP-B... ATTACHMENT LUG FOR SUPPORTS RR-SS2-8 AND RR-H7-B...
KR-BK1-3B RR-B 1 B10.30 LUG SS 731E225 PT 3 RR PMP-18... ATTACHMENT l LUG FCR SUPPORTS RR-SSS-B i AND RR-H6-8... >
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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . .m , _ _ . _ _ _ _ . - _ _ _ _ . _ _ _ _ _ _ _ , _ . _ _ _ _ . _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ . _ _ . _ _ _ _ . . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _
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'. CODE CASE N-509 .
COOPER NUCLEAR STATION -
IWB-2500-1 CAT: 8-K-1 INSERVICE INSPECTION PROGRAM REV: 2 '
REACTOR WATER CLEANUP SYSTEM THIRD INTERVAL ,
P I PE . . . . . . . . . . . . . . . . . . SYSTEM. . CNT. I TEM. NO. CF I G. . . . . . S I ZE . . TKNS. . . . . MAT. . . . . I S0. . . . . . . . . . . . . . . . . EXAMS. . . . . . . . . . . . . . . . . . . . PER RELREQ REMARKS . . . . . . . . . . . . . . . . . .
CWA-sK1-24 ~ RWCU 1 810.20- HSL SS 2503-1 PT CUH-49... .
CWA-sK1-29 RWCU 1 810.20 SP-FM SS 2503-1 PT' 1 CUM-50... SUPPORT WELDED ,
TO CONT. PEN...
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.Cf9E CASE N-509 COOPER NUCLEAR STATION IWC-2500-1 CAT: C-C INSERVICE INSPECTION PROGRAM REV: 2 .
. CORE SPRAY SYSTEM THIRD INTERVAL ,
P! PE . . . . . . . . . . . . . . . . . . SYST EM. . CNT . I TEM.NO. CF I G . . . . . . S I ZE . . TKNS . . . . . MAT . . . . 150. . . . . . . . . . . . . . . . . EXAMS . . . . . . . . . . . . . . . . . . . . PER RELREQ REMARKS. . . . . . . . . . . . . . . . . . ,
CSA-CC-10 -CS-A 1 C3.20 STN 16 .375 Pt 2603-1 MT/PT . CSS-13... .
~CSA-CC-1A CS-A 1 C3.20 PC-P 16 .844 P2 CB&I-69 MT/PT CSA-X-227A... TORUS PENETRATION X-227A, [
SUCTION...
CSA-CC-38 CS-A 1 C3.20 MSL 12 .375 P1 2602-2 MT/PT CSH-1SA, LUGS WELDED TO !
PIPE CLAMP...
CSA-CC-89 CS-A 1 C3.20 IPS 12 CS 2602-2 MT/PT CSS-16... '
CSA-CC-90 CS-A 1 C3.20 IPS 12 CS 2602-2 MT/PT CSH-17A...
CSA-CC-91 CS-A 1 C3.20 IPS 12 CS 2602-2 MT/PT CSH-19A...
CSA-CC-6 CS-A 1 C3.20 PLATE 16 .375 P1 2603-1 MT/PT 1 CSN-4... ;
CSS-CC-4 CS-8 1 C3.20 PLATE 16 .375 P1 2603-2 MT/PT CSH-1...
CS8-CC-9. CS-8 1 C3.20 PLATE 16 .375 P1 2603-2 MT/PT CSH-2... t CSB-CC-1A CS-8 1 C3.20 PC-P 16 .844 P2 C8&I-69 MT/PT CS8-X-2278... TORUS !
PENETRATION X-2278, ,
SUPPLY CS '8' PMP i SUCTION...
CS8-CC-32 CS-8 1 C3.20 PLATE 12 .375 P1 2602-1 MT/PT CSH-7...
CSB-CC-51 CS-8 1 C3.20 IPS 12 .373 P1 2602 1 MT/PT CSH-10... ,
CSB-CC-57 CS-8 1 C3.20 E-LUG 12 STD F1 2602-1 MT/PT CSH 11...
CSB-CC-102 CS-8 1 C3.20 IPS 12 .375 CS 2602-1 MT/PT CSH-9A... !
CSB-CC-WR2 CS-8 1 C3.20 PLATE 16 .375 P1 KE-110.01 MT/PT CS8-WR-2, OFF TORUS PEN !'
X-2278, ALSO SEE JELCO DWG 2603-2 CSB-CC-10 CS-8 1 C3.20 STN 16 .375 P1 2603-2 MT/PT 2 CSS-14A...
16 ***
l CS-PA-A1 CS-A 1 C3.30 SP-PUMP CS 2602-2 MT/PT 'CS-PA-St... ALL ATTACHMENT WELDS ON CORE SPRAY PMP-A, BYRON f JACKSON DWG 2C-4836 CS-PB-A1 CS-B 1 C3.30 SU-PUMP CS 2602-1 MT/PT 3 CS-P8-St... ALL ATTACHMENT WELDS ON C0itE SPRAY PMP-8, BYRON JACKSON DWG 2C-4836 l 2 -
000 18 t
30 JAN S998 PAGE 1
, _ m .
CODE CASE N-509 COOPER NUCLEAR STATION -
~IWC-2500-1 CAT: C-C INSERVICE INSPECTION PROGRAM REY:,.2 HPCI SYSTEM THIRD INTERVAL ;
- PI PE. . . . . . . . . . . . . . . . . . SYSTEM. . CNT. I TEM .NO. CF I G. . . . . . SI ZE . . TKNS . . . . . . . MAT . . . . 150. . . . . . . . . . . . . . . . . . . EXAMS. . . . . . . . . . . . . . . . . . . . PER RELREQ REMARKS. . . . . . . . . .. . . . . . . . ,
a CPIS-CC-4. HPCI 1 C3.20 PLATE 16 .375 P1 2611*6 MT/PT HPH-8...
HPIS-CC-6 HPCI 1 C3.20 STN 16 .375 P1 2611-6 MT/PT HPH-9... ;
HPID-CC-16 HPCI 1 C3.20 STN 10 .938 CS 2609-1 MT/PT -HPR-7... .!
HPID-CC-70 HPCI 1 C3.20 MSL CS 2623-3 MT/PT- RFM-53... MUST REMOVE PIPE CLAMP TO ACCESS COMPLETE EXAM AREA, MSK SHOWS LUGS WELDED TO PIPE CLAMP MPID-CC-76 HPCI 1 C3.20 PLATE CS 2623-2 MT/PT RFH-41...
HPID-CC-77 HPCI 1 C3.20 PLATE CS 2623-2 MT/PT RFH-45A...
HPID-CC-78 HPCI 1 C3.20 PLATE CS 2623-3 MT/PT RFH-59...
CID-CC-79 HPCI 1 C3.20 IPS CS 2623-3 MT/PT RFM-54...
HPID-CC-80 HPCI 1 .C3.20 IPS CS 2623-3 MT/PT RFN-55...
HPIS-CC-11 HPCI 1 C3.20 STN 16 .375 P1 2611-6 MT/PT .HPH-10...
HPIS-CC-1A HPCI 1 C3.20 P-PC 16 .844 P2 CB&I-69 MT/PT HPIS-X-226... TORUS PENETRATION X-226, SUPPLY ;
HPID-CC-5 HPCI 1 C3.20 STN 10 .938 CS 2609-1 MT/PT 1 HPH-6...
HP!S-CC-22 MPCI 1 C3.20 PLATE 16 .375 P1 2611-6 MT/PT 2 HPR-11...
13 ***
mo 13 n
30 JAN 1998 PAGE 1 L
u -... ~ _ _ - - _ ._ _ _ _ . _ - -. . - - . . - _ - _ . _ , --- _ . . _ _ _ _ _ . . _ - - - . . . _ - _ _ _ . _ _ - . _ _ - . - . _ . . - - _ . - - - - . .
CODE CASE N-509 COOPER' NUCLEAR STATION IWC-2500-1 CAT: C-C INSERVICE INSPECTION PROGRAM REV: 2 , ,
MAIN STEAM SYSTEM THIRD INTERVAL . 1
- PI PE . . . . . . . . . . . . . . . . . . SYSTEM . . CNT . ' I TEM.NO. CF I G . . . . . . SI ZE . . ' TKNS. . . . . MAT. . . . 150. . . . . . . . . . . . . . . . . EXAMS . . . . . . . . . . . . . . . . . . . .' PER RELREQ REMARKS. . . . . .. . . . . . . . . . . .
' PSA-CE1-2 ' MS 1 C3.20' IPS CS 2629-1 MT/PT MSN-101A... . .i PSA-CE1-4 MS 1 C3.20 IPS 2629-1 MT/PT MSH-97... .
., PSA-CE1 5 MS 1 C3.20 2629-1 MT/PT - MSM-95A...
PSA-CE1-6 MS 1- C3.20 ' P1- 2629-1 MT/PT MSS-7...
RAS-CE1-4 MS 1 C3.20 E-L 2629-1 MT/PT MSM-114...
RAS-CE1 5 MS 1 C3.20 PLATE CS 2629-1 MT/PT MSM-99... .
RSS-CE1 2 MS - 1 C3.20 MSL CS 2629-1 MT/PT MSH-103A RSA-CC-26 MS 1 C3.20 STN 4 TYP-C P1 2614-1 MT/PT MSS-6... i MPEX-CC-14 MS 1 C3.20 P-H 20 .375 P1 2614-3 MT/PT .MSN-154A... ,
MPEX-CC-17 MS 1 C3.20 STN 20 .3 75 P1 2614-3 MT/PT MSH-155A...
-MPEX-CC-32 MS- 1 C3.20 STN 16 .375 . P1 2614-3 MT/PT MSS-4... ;
, MPEX-CC-59 MS 1 C3.20 STN - CS 2614-3 MT/PT MSM-118... .1 PSA-CE1-1 MS 1 C3.20 STN CS 2629-1 MT/PT _1 MSH-109...
RSA-CC-25 MS 1 C3.20 MSL 8 40 P1 2614-1 MT/PT 2 MSH-121... f 14 ***
- 14 -
t t
i I !
.[
I s-30 JAN 1998 PAGE 1 I
. , . - . _ . - . . n n.__-_-_. - - - - - - _ - . - _ -u-_ _-_-..__._.-._--.,--N._- _____.- --- ---_--------.__--_N
?
CODE CASE N-509 COOPER NUCLEAR STATION- t IWC-2500-1 CAT: C-C INSERVICE INSPECTION PROGRAM REV: 2 .
RCIC SYSTEM THIRD INTERVAL- .
PIPE . . .. . . . . . . . . . . . . . . STSTEM. . CN1. I TEM. NO. CFI G. . . . . . S I ZE . . T KNS . . . . . MAT. . . . . I S0. . . . . . . . . . . . . . . . . EXAMS. . . . . . . . . . . . . . . . . . . . PE R RE LREQ REMARKS . . . . . . . . . . . . . . . . . .
RWA-CC-13 RCIC 1 C3.20 P-PC 6 1.25 P2 CBRI-69 MT/PT RWA-X-224... X-224 TORUS PEN l RWA-CC-36 RCIC 1 C3.20 STN 6 .280 P1 2621-1 MT/PT RCH-5...
RWA-CC-69 RCIC 1 C3.20 IPS CS 2621-2 MT/PT RCH-33...
RWA-CC-70 RCIC 1 C3.20 PLATE ~ CS 2621-2 MT/PT RCS-15... s RWA-CC-71 . RCIC 1 C3.20- IPS CS 2621-1 MT/PT RCH-3A...
RWA-CC-52A RCIC 1 C3.20 E-L 6 .280- F1 2621-1 MT/PT 2 RCH-6... !
6 ***-
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4 30 JAN 1998 PAGE 1 t
-___-_--_ _ - _ _ ~ . . - - _ _
CODE CASE N-509 COOPER NUCLEAR STATION IWC-2500-1 CAT: C-C INSERVICE INSPECTION PROGRAM REY: 2 RESIDUAL HEAT REMOVAL SYSTEM THIRD INTERVAL ,
PI PE . . . . . . . . . . . . . . . . . SYSTEM . . CNT . I TEM . NO. C F I G . . . . . . SI ZE . . T KNS . . . . . MAT . . . . 150. . . . . . . . . . . . . . . . . EXAMS . . . . . . . . . . . . . . . . . . . PE R RELREQ REMARKS . . . . . . . . . . . . . . . . . .
RHR-CC-2A RHR-A 1 C3.10 SP-VE 46 CS SWECO.M-82454 MT/PT 2 RHHX-1A1,1A2,1A3,154...
RHR-CC-28 RHR-B 1 C3.10 SP-VE 46 CS SWECO.M-82454 MT/PT RHHX-181,182,1B3,184...
2
- CAW-CE1-3 RNR 1 C3.20 N/A N/A 2625-1 MT/PT RHH-7...
RAW-CE9-4 RHR 1 C3.20 N/A N/A 2625-1 MT/PT RMS-80...
RAW-CE1-5 RNR 1 C3.20 HSL 20 CS 2625-1 MT/PT RHS-76...
Rau-CE1-2 RHR 1 C3.20 STN N/A CS 2625-4 MT/PT RHH-12...
RHA-CE1-1 RHR 1 C3.20 N/A N/A 2625-3 MT/PT RHH-53...
CHA-CEl-2 RHR 1 C3.20 SSL 20 .375 F1 2625-1 MT/PT 1 RI-17 RHS-74...
SW-CC-6 RHR-A 1 C3.20 IPS CS 2624-3A MT/PT RHH-6t...
RPC-CC-6 RHR-A 1 C3.20 STN 20 .375 P1 2626-1 MT/PT RHH-6... FORMALLY RPA-CC-6 IN II 2-IP 3
- DCN CHANCED ID.NO REF NCR 91-088
- RAS-CEl-1 RHR-A 1 C3.20 E-L CS 2614-2 MT/PT MSH-141...
CAW-CC-92 RHR-A 1 C3.20 STN CS 2624-3A MT/PT RMS-58...
CAW-CEl-1 RHR-A 1 C3.20 IPS N/A N/A 2625-2 MT/PT Rrs-63...
RAW-CE1-2 RHR-A 1 C3.20 STN N/A CS 2625-2 MT/PT RMS-62...
CAW-CEl-7 RHR-A 1 C3.20 STN 4 TYP-C CS 2625-1 MT/PT RMS-81...
RAW-CE9-9 RHR-A 1 C3.20 HSL CS 2624-2 MT/PT RHH-95...
CHB-CC-22 RHR-A 1 C3.20 STN 20 30 P1 2624-1 MT/PT RHH-26... ,
RHB-CC-26 RHR-A 1 C3.20 P-H 20 30 P1 2624-1 MT/PT RHH-24A...
CHB-CC-37 RHR-A 1 C3.20 P-H 24 30 P1 2624-2 MT/PT RHH-938...
RHB-CC-44 RHR-A 1 C3.20 E-L 24 30 F1 2624-2 MT/PT RHH-89...
CHB-CC-49 RHR-A 1 C3.20 STN 24 30 P1 2624-2 MT/PT RHS-24... SEC.XI CREDIT F91...
CHB-CC-51 RNR-A 1 C3.20 STN 24 30 F1 2624-2 MT/PT RHS-22...
RHB-CC-56 RHR-A 1 C3.20 STN 24 30 F1 2624-2 MT/PT RHH-91...
RHB-CC-59 RNR-A 1 C3.20 STN 24 30 F1 2624-2 MT/PT RMS-21...
RHB-CC-62 RHR-A 1 C3.20 SSL CS 2624-1 MT/PT RHS-27AB&R...
CHB-CC-63 RHR-A 1 C3.20 IPS CS 2624-1 MT/PT RHH-25A...
CNS-CC-64 RHR-A 1 C3.20 IPS CS 2624-1 MT/PT RHH-24...
RHB-CC-65 RHR-A 1 C3.20 STN CS 2624-2 MT/PT RHS-20...
RHB-CC-66 RHR-A 1 03.20 PLATE CS 2624-2 MT/PT RHH-93...
CHB-CC-67 RHR-A 1 C3.20 IPS CS 2624-2 MT/PT RHH-88...
RHB-CEl-1 RHR-A 1 C3,20 HSL CS 2624-1 MT/PT RHH-27...
RHB-CE9-3 RHR-A 1 C3.20 E-L CS 2624-1 MT/PT RHH-30...
CHB-CE1-4 RMR-A 1 C3.20 IPS N/A N/A 2624-1 MT/PT RHS-50...
RHG-CC-S8 RHR-A 1 C3.20 E-H 10 .365 F1 2624-2 MT/PT RHH-99...
RPA-CC-16 RHR-A 1 C3.20 PLATE 20 .375 F1 2625-2 MT/PT RHH-1...
CPA-CC-1A RHR-A 1 C3.20 P-PC 20 1.7/16 P2 CB&I-69 MT/PT RPA-X-225A... X-225A TORUS PEN, SUPPLY, RHR 30 JAN 1998 PAGE 1
l
. CODE CASE N-509 COOPER NUCLEAR STATION IWC-2500-1 CAT: C-C INSERVICE INSPECTION PROGRAM REY: 2 -
EESIDUAL HEAT REMOVAL SYSTEM THIRD INTERVAL -
P I PE . . . . . . . . . . . . . . . . . SYSTEM. . CNT. I TEM . NO. CF I G. . . . . . $ 12E . . TKNS . . . . . MAT. . . . 150. . . . . . . . . . . . . . . . . EXAMS . . . . . . . . . . . . . . . . . . . . PER RELREQ REMARKS. . . . . . . . . . . . . . . . . . I
- A' PMP SUCTIONI.. ,
RPA-CC-20 RHR-A 1 C3.20 E-SP 16 40 F1 2624-1 MT/PT RHH-21...
KPC-CC-1A RHR-A 1 C3.20 P-PC 20 1.7/16 P2 CB&I-69 MT/P1 -
RPC-X-2258... X-225B TORUS PEN, SUPPLY, RHR
'C' PMP SUCTION...
RAW-CEl 14 RHR-A 1 C3.20 N/A N/A 2624-3A MT/PT RMS-57...
RAW-CE1-15 RHR-A 1 C3.20 N/A N/A 2624-3A MT/PT RHH-61...
RTC-CC-20A RHR-A 1 C3.20 PLATE N/A N/A F1/F1 2624-1 MT/PT RHH-23... '
RPC-CC-24A RHR-A 1 C3.20 E-H 16 40 F1 2624-1 MT/PT RMS-55... ;
RAW-CE1-12 RHR-A 1 C3.20 LUG N/A . CS 2624-3A MT/PT 1 RHH-59... i RPA-CC-9 RHR-A 1 C3.20 STN 20 .375 P1 2626-1 MT/PT 2 RHH-2... FORMERLY EXAMINED AS RPC-CC-9
- DCN NO. C93-0385 2/93 TO CHANGE WELD ID.WO REF NCR 91-088 * [
KMB-CC-53 RNR-A 1 C3.20 E-L 24 30 F1 2624-2 MT/PT 3 RHH-90... E RHB-CE1-2 RHR-A 1 C3.20 E-L 16 CS 2624-1 MT/PT 3 RHH-28...
RPC-CC-10 RHR-A 1 C3.20 STN 20 .375 P1 2626-1 MT/PT 3 RHH-5... FORMERLY ,
EXAMINED AS RPA-CC-10 IN
- INT 2, PER 2
- DCN NO.
C93-0385 2/93 TO CHANGE [
WELO ID.NO REF NCR 91-088 i
RHE-CC-3 RHR-B 1 C3.20 E-SP 10 .365 F1 2624-7 MT/PT RHH-140...
RPB-CC-6 RHR-B 1 C3.20 P-H 20 .375 P1 2626-2 MT/PT RHH-19... t RPB-CC-7 RHR-B 1 C3.20 HSL 20" .375 P1 2626-2 MT/PT RHH-18A... I RBS-CE1-1 RHR-B 1 C3.20 E-L CS 2614-2 MT/PT MSH-139... !
RCT-CC-27 RHR-B 1 C3.20 IPS CS 2624-38 MT/PT RHH-62...
RCT-CEl-1 RHR-B 1 C3.20 SAD N/A N/A 2624-3A MT/PT RHH-57... [
RCT-CE1-2 RHR-B 1 C3.20 P-H N/A N/A 2624-3A MT/PT RHH-54...
KCT-CE1-4 RHR-B 1 C3.20 HSL CS 2624-3B MT/PT RHH-50...
RMC-CC-32 RHR-B 1 C3.20 E-L 20 30 F1 2624-3B MT/PT RHH-48...
RMC-CC-36 RHR-B 1 C3.20 P-H 2624-3B MT/PT RHH-47... ,
RMC-CC-41 RHR-B 1 C3.20 P-H 24 30 P1 2624-5 MT/PT .RHH-64...
RKC-CC-51 RHR-B 1 C3.20 E-SB 24 30 F1 2624-5 MT/PT RHS-30... f RMC-CC-52 RHR-B 1 C3.20 E-L 24 30 F1 2624-5 MT/PT RHH-68... I RMC-CC-61 RHR-B 1 C3.20 IPS CS 2624-3B MT/PT RHH-118A...
, RNC-CC-62 RHR-B 1 C3.20 IPS CS 2624-3B MT/PT RHH-47A... [
RNC-CC-63 RHR-B 1 C3.20 PLATE CS 2624 5 MT/PT RHH-64B... '
RNC-CE1-1 RHR-B 1 C3.20 IPS N/A N/A 2624-38 MT/PT RHH-44A...
KHC-CE1-2 RHR-B 1 C3.20 E-L N/A N/A 2624-3B MT/PT RHH-43... I RHD-CE1-1 RHR-B 1 C3.20 E-L CS 2624-6 MT/PT RHH-139...
RHD-CE1-3 RHR-B 1 C3.20 MSL N/A CS 2624-6 MT/PT RHH-136... .
RHD-CE1-6 RHR-B 1 C3.20 STN 2624-6 MT/PT RHH-133... I
\
30 AN 1998 PAGE 2
l I
CODE CASE N-509 COOPER NUCLEAR STATION IWC-2500 1 CAT: C-C INSERVICE INSPECTION PROGRAM REV: 2 .
RECIDUAL HEAT REMOVAL SYSTEM THIRD INTERVAL -
P I PE . . . . . . . . . . . . . . . . . . SYSTEM . . CNT . I T EM.NO. CF I G. . . . . . SI ZE . . TKNS . . . . . MAT . . . . 150. . . . . . . . . . . . . . . . . Eh AMS . . . . . . . . . . . . . . . . . . . . PER RE LREQ REMARKS . . . . . . . . . . . . . . . . . .
RPB-CC-10 RHR-B 1 C3.20 STN 20 .375 P1 2626-2 MT/PT RHH-18... -
RPB-CC-15 RHR-B 1 C3.20 SP 20 .375 P1 2625-4 MT/PT RHH-17...
RPB-CC-1A RHR-B 1 C3.20 P-PC 20 1.7/16 P2 CBRI-69 MT/PT RPC-X-225C... X-225C TORUS PEN, SUPPLY, RHR
'B' PMP SUCTION...
RPB CC-20 RHR-B 1 C3.20 E-H 16 40 F1 2624-3C MT/PT RHH-39...
RPB-CC-28 RHR-B 1 C3.20 STN 16 40 P1 2624-3C MT/PT RHS-42...
RPB-CC-32 RHR-B 1 C3.20 LUG 16 40 F1 2624-3C Mr/PT RHH-40...
RPD-CC-14 RHR-B 1 C3.20 PLATE 20 .375 F1 2625-2 MT/PT. RHH-14...
RPD-CC-19 RHR-B 1 C3.20 E-H 16 40 F1 2624-3C MT/PT RHH-38... i RPD-CC-1A RHR-B 1 C3.20 P-PC 20 1.7/16 P2 CB&t-69 MT/PT RPD-X-2250... X-2250 ;
'D' PHP SUCTION... l RPD-CC-34 RHR-B 1 C3.20 IPS CS 2624-3C MT/PT RHH-41A... i RBW-CE1-10 RHR-B 1 C3.20 STN CS 2624-3B MT/PT RHS-39...
RBW-CE1-11 RHR-B 1 C3.20 IPS N/A CS 2624-3B MT/PT RHH-46... ,
RJW-CE1-12 RHR-B 1 C3.20 E-L CS 2624-3B MT/PT RHH-117A... !
RHD-CEl-11 RHR-B 1 C3.20 IPS 2624-6 MT/PT RHH-132...
RHC-CE1-3 RHR-B 1 C3.20 E-L N/A CS 2624-3B MT/PT 1 RHH-42...
RHC-CC-58 RHR-B 1 C3.20 LUGS 24 30 P1 2624-5 MT/PT 2 RHH-69...
82 *** i RH2-PC-Al RHR-A 1 C3.30 SP-PU CS 2624-1 MT/PT RI-18 RHR-PC-S1... ALL ,
ATTACHMENT WELDS ON RHR PMP-C, REFERENCE BINGHAM PMP DWG Z-6363...
RHR-PA-A1 RHR-A 1 C3.30 SP-PU CS 2624 1 MT/PT 3 RI-18 RPA-PA-St... ALL ATTACHMENT WELDS ON RHR PMP-A, REFERENCE BINGHAM ,
PMP DWG Z-6363...
RHR-PB-A1 RHR-B 1 C3.30 SP-PU CS 2624-3C MT/PT RI-18 RHR-PB-St... ALL ATTACHMENT WELDS ON RHR i PMP-8, REFERENCE BINGHAM i PMP DWG Z-6363...
KHR-PD-A1 RHR-B 1 C3.30 SP-PU CS 2624-3C MT/PT RI-18 RHR-PD-S1... ALL ATTACHMENT WELDS ON RHR PMP-D, REFERENCE BINGHAM PMP DWG Z-6363...
4 *** ~
M 30 JAN 1998 PAGE 3
- L t
h 5.
5 CODE CASE N-509 COOPER NUCLEAR STATION IWC-2500-1 CAT
- C C INSERVICE INSPECTION PROGRA4 REY: 2 _
SCRAM DISCMARGE VOLUME SYSTEM THIRD INTERVAL !
PI PE . . . . . . . . . . . . . . . . . . SYSTEM . . CNT. I TEM.NO. CF I G. . . . . . SI ZE . . TKNS. . . . . MAT . . . . 150. . . . . . . . . . . . . . . . . EXAMS . . . . . . . . . . . . . . . . . . . . PER RELREQ REMARKS. . . . . . . . . . . .. . . . . . . I e
~
SDS-CEl-21 Sov 1 C3.20 HSL N/A CS $1W13095.19-EP-18-2 MT/PT 1 RI-17 PSA-i...
j ... l l
- 1 I-I' f
I L
f i
t L
i
-l, i
h 30 JAN 1998 PAGE 1 1
.I i
____-.____m__....m.m -
____ _ __ ____ _ _ _ _ _ - . . . _ _ _ _ . _ . _ _ . _ _ _ _ . _ . _ . . __.__.____mm._ _ _ . ____.___.___m.______m___ . . _ ._ _ _ _ _ _ . . _ . .
Attachincnt 3 to NLS980145
. 1 Page Total
, Attachment 3 Drawing of Service Water Pump Discharge IIcad
l Service Water Pump l l (From Drawing B5800*1F-6921)
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1
. i l ATTACHMENT 3 LIST OF NRC COMMITMENTS l
Correspondence No:NLS900145 The following table identifies those actions committed to by the District in this document. Any other actions discussed in the submittal represent intended or planned actions by the District. They are described to the NRC for the NRC's information and are not regulatory commitments. Please notify the NL&S Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.
COMMITTED DATE COMMITMENT OR OUTAGE None NA l
l PROCEDURE NUMBER 0.42 l REVISION NUMBER 6 l PAGE 9 C F 13 l