ML072180237
| ML072180237 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 07/31/2007 |
| From: | Bethay S Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2.07.065 PNPS-RPT-07-00001, Rev. 0 | |
| Download: ML072180237 (14) | |
Text
SEn tergy Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 Stephen J. Bethay Director, Nuclear Assessment July 31, 2007 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station Docket 50-293 License No. DPR-35 Pilgrim Refueling Outage (RFO) - 16, Inservice Inspection (ISI) Summary Report LETTER NUMBER:
2.07.065
Dear Sir or Madam:
The enclosed report provides a tabulation of all inservice examinations and code repairs/replacements performed at Pilgrim Station from the end of RFO-15 through RFO-16.
Copies of the examination vendor reports and data sheets are retained at Pilgrim Station for NRC review, if required.
This submittal fulfills the requirements of ASME Section Xl, 1989 Edition, Paragraph IWA-6230.
There are no commitments contained in this letter.
If you have any questions regarding the information contained in this letter, please contact Ed Sanchez at (508) 830-8877.
Sincerely, S tephen J.
tha Director Nuclear Safety Assessment
Enclosure:
Inservice Inspection Summary Report for Refuel Outage 16 at Pilgrim Nuclear Power Station, dated July 27, 2007 (11 pages)
,&lL(7
Entergy Nuclear Operations, Inc.
Letter Number: 2.07.065 Pilgrim Nuclear Power Station Page 2 cc:
Mr. James S. Kim, Project Manager Office of Nuclear Reactor Regulation Mail Stop: 0-8B-1 U.S. Nuclear Regulatory Commission 1 White Flint North 11555 Rockville Pike Rockville, MD 20852 U.S. NRC, Region 1 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector Pilgrim Nuclear Power Station
ENCLOSURE TO ENTERGY LETTER No. 2.07.065 Inservice Inspection (ISI) Summary Report for Refuel Outage 16 at Pilgrim Nuclear Power Station, Dated July 27, 2007 (11 pages) 207065 Enclosure
ENCLOSURE TO ENTERGY LETTER No. 2.07.0651 NUCLEAR QuAV RALAeO EN-C-47 REV.2 En/eW*
MANAGEMENT ENC-4 MANUALEM T
IIUS PAGE 13 OF 22 Engineering Repodts ATTACHMENT 9.1 ENGINEERING REPORT COVER SHEET & INSTRUCTIONS SHEET I OF 1
- - EnteW Engineering Report No.
PNPS-RPT-07-00001 Rex.
Page I
of it Attachrnent I pages 1-3j pages I-ti! pages 1-2 RGY NUCLEAR g Report Cover Sheet ring Report
Title:
FIRST OUTAGE, FIRST PERIOD OF FOURTH INTLRVAl.
ENTEI Engineerinj ENngine*o PNPS oWNER'S ACTIVITY REPORT (OAR) for Engineering Report Type:
El Cancelled El New 0
Revision Superseded El Applicable Site(s) iPI 0 tOl Q.
DR.N No. Q]
[P2 1]
AN02 C]
NIA; 0-IP3 El EC11 0
RBS C3 VY El WF3 C3 wPO El Report Origin:
(
Entergy C] Vendor Vendor Document No.:
r-ia Quality-Related:
a Yes Eli No Prepared by:
Richard Par-.ee /
Responsible Engineer (Print 4arneiSign)
Design Verifier (if required) (Print Name Sign)
Date: 20&LýQ 7 Design Venrfied, Re% ieed by:
/,-j~~,oio Reviewer (Print Namre S igni) kcvicwed by'-
C.-ur Hanson (lI S8WdK_,,
.:ar f r e: Z/O217 Date:
-r~7 ippruoed by:
S.eve W
,Oda:
Supervisor (Printl Narne.Sigd)
Ff.$~S'ection XI oeProgam plans per ENN-DC-120, it'retuired
Enclosure to Entergy Letter No. 2.07.065]
FORM OAR-I OWNERS ACTIVITY REPORT Report Number PNPS-RPT-07-00001, Rev. 0 Owner Entergy Nuclear Northeast, 440 Hamilton Ave, White Plains, New York 10601 (Name and Address of Owner)
Plant PILGRIM NUCLEAR POWER STATION, 600 Rocky Hill Road, Plymouth, MA 02360 (Name and Address of Plant)
Plant Unit I
Commercial Service Date June 8, 1972 Refueling Outage Number 16 Current Inspection Interval (1st, 2nd, 3rd, 4th, Other)
Current Inspection Period (1st, 2nd, 3rd)
I 51 Edition and Addenda of Section XI applicable to the Inspection Plan 1998 Edition, 2000 Ac Date and Revision of Inspection Plan:
PNPS ISI Program Plan, No. PNPS-RPT-05-001 Rev. 0 Idenda Edition and Addenda of ASME Section Xl applicable to Repairs and Replacements, if different than the Inspection Plan N/A CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owners Activity Report are correct, and that the examinations, tests, repairs, replacements, evaluations and corrective measures represented by this report conform to the requirements of Section XI.
Certificate of Authorization No.
N/A Expiration Date N/A (If applicabl*
Signed_
(IefO sdeigne Date 07 Titl Owner or Owner' s designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Massachusetts and employed by HSB-CT of Hartford, Connecticut have inspected the components described in this Owners Report during the period 5/10/2005 to 5/5/2007
, and state that to the best of my knowledge and belief, the Owner has performed all the activities described in the Repair/Replacement Plan in accordance with the requirements of Section Xl.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the activities described in the Repair/Replacement Plan. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.
tC Commissions /14dl//Wl I*'/6*
,1/
F/
Inspector's Signature Date 7/; itý7 National Board, State, Province, and Endorsements
FOURTH INTERVAL IEnclosure to Entergy Letter No. 2.07.065 1PNPS-RPT-07-OOO1 ATTACHMENT I First Refueling Outage First Period Refuel Outage 16 TABLE I Total Total Total Total Examinations Examinations Examinations Eaminations Credited (%) To Examination Required for the Credited for Credited (%)
Date for the Category Interval this Period for the Period Interval Remarks TPermanent relief for the period of the initial license from the code requirements for inspection of RPV circumferential welds is approved in B-A 39 0
0%
0%
relief PRR-28.
Table IWB-2500-1 (Note 2) allows a maximum credit of 50% for the 1st B-D TZ56ZZ 10 18%0/
18%
period.
B-F welds are inspected under Category R-A of the PNPS Risk-Informed Program and the PNPS augmented BWRVIP-75A IGSCC weld inspection program. Extent and frequency are in accordance with BWRVIP-75A B-F 0
0 0%
I 0%
criteria.
B-G-1 23 1
4%
4%
L B-G-2 i
71 I
14 20%
]
20%
.4...~~~..
~__
1 t [B-J welds are inspected under Category R-A in the PNPS Risk-Informed
!Program and the PNPS augmented BWRVIP-75A IGSCC weld inspection B-J;.3/40 0
0 0%
- i.
0%
1 program.
B-K 10 1
4 4 0 %
40% o 10 I.......
L.........
B-L-0 iFo f
o~0 o applicable to PNPS (pumps do not hav csingwls
... ~t'Z-.'~-'
44
. 4 t;t ~
~
!Once per interval B-L-2 1 (1 of 2 pumps) 1 1
50%
50%
Recirc pump P-201B was disassembled for maintenance during RFO16.
'M..IS*N, t
At.
',4
.4 '. 4 C.
-r----1-4wr 0"~r 0%
0%4.,4;4'4441
~
.4
~~1 1.,~.,..,.
-5:1 444-44..
Ale.4'4
.44',-..
~
Page 1 of 3
FOURTH INTERVAL Enclosure to En tergy Letter No. 2.07.065 PNPS-RPT-07-O 1
ATTACHMENT I First Refueling Outage First Period Refuel Outage 16 1- -.
w t
.!X
'1.
-~
V.
01
ý Total Total Total Total Examinations Examinations Examinations Eaminations Credited (%) To Examination Required for the Credited for Credited (%)
Date for the Category Interval this Period for the Period Interval Remarks
!Exam required only when a valve is disassembled for maintenance, repair, ior volumetric exam. Exams are limited to at least one valve within each Once per interval
- group of valves that are of the same size, constructional design and B-M-2 (23 of 48 valves) 21%
21%
!manufacturing method, and that perform similar functions in the system.
Exams conducted within this code category are performed in accordance B-N-11 3
1 1
33%
33%
.l..
l "Exams conducted within this code category are performed in accordance B-N-2 72 0
t 0 t
q%
I 0%
with the PNPS BWRVIP vessel inspection program.
y B-O 4
0 I
0.0%
0%
0% of peripheral CRD housings (i.e. 10% of 36 housings)
B-P 25 5
20%
20%
Includes Class 1 System Pressure Test C-A 5
2 40%
1 40%
j c-B 6
00%
0%
g..
Mt~
t
,~ A~IW C-C 31 6
19%
19%
l o%.o C-F-1 12 0
0%
0%
C-F-2 82 16 20%
20%
C-G 11 2
18%
18%
___-AA_
30t 13
..3
.j.
C-H
.30 13 43%
43%
!includes SLT RHR-13 D-A 12 i
2 17%
17%
D-B 69 9
13%
13%/4.gtA..tj4;,iW' a *4 2
Zs~'
tt~
a
'~'-
gr.~-<
5 "A
F3ý YM
.2 4j3'"2 222 Page 2 of 3
FOURTH INTERVAL IEnclosure to Entergy Letter No. 2.07.065 PNPS-RPT-07-00001 First Refueling Outage ATTACHMENT I First Period Refuel Outage 16
$4 t~...4
- % iW d~.4 rN
.~.4.
- 94.
,4,~
44,~~444
~,.,4~rj~7s'r
-e.~7.4%.k$4S4r t'~;,,.
- r.
4.~$',j~4..
4 ~474.~j4J.4;.
tt~SS Total Total Total Total Examinations Examinations Examinations Eaminations Credited (%)To Examination Required for the Credited for Credited (%)
Date for the Category Interval this Period for the Period Interval Remarks The General Visual Examination is required once each period. A VT-3 examination of the BWR Vent system and wetted surfaces of submerged E-A 38 16 42%
42%
areas is required once per interval.
E-C 24 22 92%
92%
CLASS 1 t
t.,ys SNUBBER ATTACHMENTS:
14 3
i 21%
21%
i CLASS 2 SNUBBER ATTACHMENTS 2
0 0%
0%
CLASS3 3 SNUBBER I
ATTACHMENTS!
1 0
0%
1 0%
SUPPORTS OTHER THAN PIPING SUPPORTS 21 3
i
- q.
140/°c7 14%
TOTAL !
1 CATEGORY F-A 136 I
32 24%
1 24%
..,.X,.,'
.- *q
.t*.
4*
.4 J
" 4, 2
.W.*
74,74*
44,4. 44,, 4 7.4'
.4.4.;.,.,
.,t
~~0 W W4.1 FI PNPS has a Class 1 Risk-Informed inspection program based on CC N-578 CLASS 1 1
71 I
_and EPRI Topical Report TR-1 12657.
CLASS 2 0
PNPS has a Risk-Informed inspection program for Class 1 only CLASS 3 0
5.PNPS has a Risk-Informed inspection program for Class 1 only
.i-A 71 11 150/%
15%
- .4 4...
i 7
$t4 4 s4:$
4 T4 ;yi..*Y 4j5.4~3 4
yU43s.~ '..h 47:
,,..... 4. 5 45......
Page 3 of 3
FOURTH INTERVAL Enclosure to Entergy Letter No. 2.07.065 PNPS-RPT-07-00001 ATTACHMENT 2 First Refueling Outage First Period Refuel Outage 16 TABLE 2 Flaw or Relevant Condition Found During Scheduled Examination Section XI Examination Category Item Number Item Description Flaw Characterization (IWA-3300) or Test (YesINo)
Results Accepted for continued service after threads of five bolts were re-conditioned per Maintenance Request 02120627. As-found Class 1 pressure
, Bolting on valve MSIV 203-2C found condition documented per CR-PNP-2007-B-G-2 B7.70 retaining bolting with thread damage Yes 1986.
Accepted for Continued Service - The non-pressure boundary leakages were either stopped by mechanical methods (e.g.
I tightening valve packing) or stopped leaking I
due to thermal expansion associated with higher operating temperatures during Non-pressure boundary leakage startup operations. Leakages were C
Sdiscovered during performance of the Idocumented and evaluated per CR-PNP-i Class 1 System Class 1 System Pressure Test following I2007-2379 and Maintence Requests B-P i
B15.50 Pressure Test RFO16 Yes 05120716 and 07107808.
-i
_Accepted for continued service after valve c
v C
3 fnon-pressure boundary seating surfaces HPCI check valve 23-CK-2301-7 found
ýwere re-conditioned per Maintenance during RFO16 maintenance to have Request P9600772 and re-inspected.
corrosion and wear on valve disc Condition documented per CR-PNP-2007-B-M-2 812.50 Valve Internals seating surfaces.
No 1805.
Page 1 of 4
FOURTH INTERVAL TEnclosure to Entergy Letter No. 2.07.065 2PNPS-RPT-07-001 ATTACHMENT 2 First Refueling Outage First Period Refuel Outage 16 TABLE 2
.~....
~ Illl.
.llIll l=l m V Flaw or Relevant Condition Found During Scheduled Examination Section XI Examination Category Item Number Item Description Flaw Characterization (IWA.3300) or Test (YeslNo)
Results Accepted for Continued Service - Areas with coating degradation and surface corrosion were identified but no structural degradation was identified. The 1containment if fully functional and no I significant degradation is expected during operation per CR-PNP-2007-2003 Drywell-to-torus vent system interior disposition. Identified areas to be recoated i
surfaces have areas of degraded under Maintenance Request 07106963 E-A E1.20 BWR Vent System i
coatings and moderate corrosion.
Yes during future outages.
-_-Accepted for Continued Service - Areas of flaking coating and local surface rusting lwere detected during the IWE General Visual Walkdown of primary containment surfaces during RFO16 as documented in CR-PNP-2007-2093. No evidence of
!I
'degradation that could affect containment Protective coatings of drywell and torus structural integrity, leak tightness or interior and exterior surfaces have containment support functionality were conditions that exceed acceptance detected. Maintenance Requests 07107301 IWE General Visual criteria in Engineering Standard ENN-and 07107302 were initiated to perform E-A E1.11 Walkdown EP-S-001 Yes coating repairs during RFO17.
Page 2 of 4
FOURTHINTERVAL Enclosure to Entergy Letter No. 2.07.065 IPNPS-RPT-07-0001 ATTACHMENT 2 First Refueling Outage First Period Refuel Outage 16 TABLE 2 Flaw or Relevant Condition Found During Scheduled Examination Section Xl Examination Category Item Number Item Description Flaw Characterization (IWA-3300) or Test (Yes/No)
Results Accepted for Continued Service - Water was found in the collection container under one annulus air gap drain line in Torus Room prior to flooding down during RFO16 as documented in CR-PNP-2007-2050.
Chemical testing of the collected water determined it to be RBCCW water (due to presence of nitrates) and did not originate lon the refuel floor. Source of the water was eventually determined to be water from Water found in collection container venting activities during valve testing on top under one annulus air gap drain line in
'_Accepted for Continued Service - As-built RHR pipe support H--101-1-80 found condition is documented on CR-PNP-2007-i during RFO16 to have four un-1005. Support drawing will be revised to documented pieces of electrical conduit reflect as-built condition per CR-PNP-2007-F-A FI.20-A Pipe Support welded to support members.
Yes
- 00831 CA-008.
Accepted for Continued Service - As-found 1 RBCCW pipe support H-30-1-66 found condition documented on CR-PNP-2007-during RFO16 to have corroded sliding 1072. Support corroded surfaces were surfaces exceeding inspection cleaned per Maintenance Request F-A I
F1.30-B1 Pipe Support procedure acceptance criteria.
Yes 107105090 and accepted.
Page 3 of 4
FOURTH INTERVAL Enclosure to Entergy Letter No. 2.07.065 1PNPS-RPT.07-0001 ATTACHMENT 2 First Refueling Outage First Period Refuel Outage 16 T ABLE 2.
Flaw or Relevant Condition Found During Scheduled Examination Section Xl Examination Category Item Number Item Description Flaw Characterization (IWA-3300) or Test (YesINo)
Results Snubber as-found condition during RFO16 documented as low fluid level in CR-PNP-2007-1298. Condition was found as part of an expanded inspection sample in response Ito suspected seal issues in all 20 kip snubbers that were rebuilt during 2005.
Component was removed and functional testing determined the snubber to be operable. Snubber was subsequently HPCI snubber H-23-1-12SS (23-20-36) replaced during RFO16 prior to resuming F-A _
F1.20-C Hydraulic Snubber
__found during RFO16 with low fluid.
I No operation.
Accepted for continued service after Surface scratching caused on and
,scratches were removed by mechanical around Core Spray piping butt weld 14-surface conditioning methods in accordance B-20 while mechanically removing grout with CR-PNP-2007-1910.
I Class 1-circumferential from around pipe weld surface in Surface scratches causes by grout removal R-A R1.20 weld preparation for scheduled ISI exam.
No tools were shallow and minor in nature.
Page 4 of 4
FOURTH INTERVAL Enclosure to Entergy Letter No. 2.07.065 PNPS-RPT-07-00001 I
I ATTACHMENT 3 First Refueling Outage First Period Refuel Outage 16 I
TABLE 3 Repair/Replacement or Corrective Measure Flaw or Relevant Condition Found During Scheduled Examination or Test (YesINo)
Close Date Repair/Replacement Plan Number Item Description and Description of Work TABLE 3
1.
Replacement 1
.Repair
- 1.
Replacement 1.
Replacement 2
Replacement 2 -
Replacement 2
Replacement 2
Repair 2
Replacement 3
Replacement 3
Replacement 3
Replacement 3
Replacement 3
Replac ement.
3 Replacement 3
Replacement 3
Replacement 3
Replacement 3
Replacement 3
Repair 3
Replacement 3
Replacement Replace CRDs in RFO16 at 23 core locations Code-rejectable flaw in nozzle-to-safe end weld 2R-N2K-1 was *
,repaired by installation of..a fullstructural weld. overlay.
Replace Recirc pump P-201 B rotating element & cover bolting
- Replace RPV head vent piping flange studs and nuts with new material Replace CRD mechanical snubber SS-3-25-06
.Replace RHR MO1001-34A valve disc
'.Replace CRD mechanical snubber SS-3-25-07 Repair RHR MO1001.-7C valve disc Replace RHR Hx E-207B studs and nuts
- Replace pressure-retaining pump columns, bolting, expansion
.joint in SSW pump P-208A
- Replace parts P-202C discharge check valve 30-CK-419
- Replace parts P-202D discharge check valve 30-CK-422
,Replace in-kind TBCCW Hx E-122B bolting (studs/nuts)
.Replace in-kind SSW piping bolting (studs/nuts)
Replace _RBCCW pump P-202B mechanical seal (in-kind)-
Replace of RBCCW pump P-202B mechanical seal (in-kind)
Replace parts SSW pump P-208E, exp jount, air vent vlv, disch
- check vlv 29-CK-3880E.
Modify pressure-retainingpart (disc) in SSW valve 29-HO-3A i Replace parts RBCCW pump P-202D suction & disc.h flange bolting Replace SSW 29-HO-3829 valve Yes No No No No No No
-No.
No No No No No No No No No No No No No 4/20/2007 5/7/2007 8/19/2007 4/13/2007 4/19i2007 4/20/2007' 4/30/2007 5/7/2007 6/3/2005 6/21/2005 6/29/2005 1/25/2006 2/1/2006 2/1/2006 2/112006 3/20/2006 6/1/2006 No MR 05110469 MR 06100506 MR 03121989 MR 05116947 MR 05117985 MR 06101196 MR 05117984 MR 07105779 MR 07105865 MR 03102360 MR 05104647 MR 05104645 MR 02104136 MR 02104136 MR 02104136 MR 02104136 MR 06103973 MR 06108261 7/5/2006 MR 06107824 10/18/2006 MR 06115164 11/2/2006 MR 05112179 4/18/2007 MR P9500772 Page 1 of 2
FOURTH INTERVAL Enclosure to Entergy Letter No. 2.07.065 PNPS-RPT-07-O0001 I
I ATTACHMENT 3 First Refueling Outage First Period Refuel Outage 16 TABLE 3 Flaw or Relevant Repair/Replacement Condition Found During CODE or Corrective Scheduled Examination or Close Repair/Replacement CLASS Measure Item Description and Description of Work Test (YesiNo)
Date Plan Number 3
Replacement i Replace SSW 29-HO-3A and -5A valves No 4/20/2007 MR 06115726 3
Replacement Replace SSW 29-HO-3800 valve No 4/20/2007 MR P9402370 3
Replacement Replace SSW 29-HO-3814 valve No 4/20/2007 MR P9900388 3
Replacement.....
Replace SSW 29-HO-381 5 valve.
No 4/20/2007, MR P9900389 3
Replacement
'Replace SSW spool JF-29-1 -7 No 4/20/2-07 MR 05117196 3
Replacement *Replace SSW spool JF-29-2-2 No 4/20/2007 MR 05117197 3
Replacement Replace RBCCW P-202C pump suction valve 30-HO-38 No 4/23/.2007 MR 04106576 3
Replacement Replace SSW 29-HO-3842 valve No 4/24/2007 MR P9500773 3
Replacement Replace parts RBCCW pump P-202D No 5/4/2007 MR 07102534 Page 2 of 2