ML092450592
| ML092450592 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 08/24/2009 |
| From: | Bethay S Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PNPS-NE-09-00002, Rev 0 | |
| Download: ML092450592 (8) | |
Text
SEntergy Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 Stephen J. Bethay Director, Nuclear Assessment August 24, 2009 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) -17 In-Service Inspection (ISI) Owners Activity Report (OAR)-1 Submittal LETTER NUMBER:
2.09.053
Dear Sir or Madam:
By this letter Entergy submits to NRC the attached Pilgrim Nuclear Power Station In-Service Inspection (ISI) Owners Activity Report (OAR-i) Results Report for Refueling Outage (RFO)-17 in accordance with ASME Section Xl and NRC approved Code Case N-532-4.
The report contains a tabulation of all in-service examinations and Code repairs/replacements performed at Pilgrim Station from the end of RFO-16 through RFO-17.
Copies of the examination vendor reports and data sheets are retained at Pilgrim Station for NRC review, if required.
Pilgrim is in the Fourth In-Service Inspection (ISI) Interval and is subject to the 1998/2000 Addenda of ASME Section XI.
AN77
Elntergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station Letter Number: 2.09.053 Page 2 There are no new commitments made in this letter.
If you have any questions regarding the information contained in this letter, please contact Pilgrim Licensing Manager, Joseph R. Lynch at (508) 830-8403.
Sincerely, Stephen J. ethay Director Nuclear Safety Assessment WGL/Lic
Attachment:
In-service Inspection Summary Report for Refueling Outage 17 at Pilgrim Nuclear Power Station, Engineering Report No. PNPS-NE-09-00002, Rev. 0, dated August 23, 2009 (5 pages) cc:
Mr. James S. Kim, Project Manager Office of Nuclear Reactor Regulation Mail Stop: 0-8C2 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
Attachment to Enterqy Letter No. 2.09.053 In-service Inspection Summary Report for Refueling Outage 17 at Pilgrim Nuclear Power Station Engineering Report No. PNPS-NE-09-00002, Rev. 0 Dated August 23, 2009 (5 pages)
ATrACHmENT 9.1 SHEET I OF I ENGINEERING REPORT COVER SHEET & INSTRUCTIONS Engineering Report No PNPS-NE-09-00002 Rev 0
Page 1
of 5 Attachment I pages: 1-2 pages: 1 ENTERGY NUCLEAR Engineering Report Cover Sheet Engineering Report
Title:
PNPS OWNERS ACTIVITY REPORT(OAR) FOR SECOND OUTAGE FIRST PERIOD OF FOURTH INTERVAL Engineering Report Type:
El Cancelled E]
New Z
Revision Superseded 1]
Applicable Site(s)
EC3 El ECH F1 JAF EI GGNS EI PNPS 09 RBS El VryL WF3L WPO 11 PLPElI DRN (EC) No. [IN/A; 0-Report Origin:
S Entergy LI Vendor Vendor Document No.:
N/A Quality-Related:
Z Yes El No Katie Bienvenue Itt iXo1
, Lt Date:
- L*I '1 Prepared by:
Design Verified/
Reviewed by:
Reviewed by*:
Approved by:
Responsible Engineer (Print Name/Sign)
N/A Design Verifier (if required) (Print Name/Sign)
RichPardee 2
9 6
Reviewer (Print Name/Sign)
Date: - t,> I Fý Date:
/.f/4Z Curt Hanson (HSB) 2
--.Date:
ANII (if required) (Print Name/Sign)
Steve Woods Supervisor (Print Name/Sign)
Date: 89 2_3 aZa9
- For ASME Section XI Code Program plans per EN-DC-120, if required
FORM OAR-I OWNERS ACTIVITY REPORT Report Number PNPS-NE-09-00002, Rev. 0 Plant PILGRIM NUCLEAR POWER STATION, 600 Rocky Hill Road, Plymouth, MA 02360 (Name and Address of Plant)
Plant Unit 1
Commercial Service Date June 8. 1972 Refueling Outage Number 17 Current Inspection Interval Current Inspection Period 4th (1st, 2nd, 3rd, 4th, Other) 1st (1st, 2nd, 3rd)
Edition and Addenda of Section Xc applicable to the inspection plans 1998 Edition, 2000 Date and Revision of Inspection Plan:
PNPS 151 Program Plan. No. PNPS-RPT-05-001 Rev. 1 Addenda Addenda the inspection plans NIA Code Cases used: Reference PNPS - RPT-05-001., Rev 1 for code cases used CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of F 17 conform to the requirements of Section Xl.
Signed 4/?
"/4 "-w ftlt.
Date___
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 items described in this Owners Report, and state that, to the best of my knowledge and belief, the Owner has performed all the activities represented by this report in accordance with the requirements of Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report.
Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Commissions /V6/1I9/,
,4&'.T M41*j 1
Inspector's Signature National Board, State, Province, and Endorsements Date S/
/
FOURTH INTERVAL PNPS-NE-09-00002 Second Refueling Outage ATTACHMENT 1 First Period Refuel Outage 17 IESWITH FLAWS~ -O RLEVN COO STATRQIE EVALUATION FOR CONTINU)ED SERVICE Examination Category and Item Number Item Description Evaluation Description
..Accepted for continued service. A fracture mechanics evaluation of the a to flange weld (RPV-HF) flaw indication in the RPV closure head has been evaluated in accordance
.* :IS exminaionofteRPhead g
- (-
):
.with.ASME BPVC SC XI IWB-3600..& Appendix A and found acceptable identified a linear indication requiring further evaluation to w
B.
S&xd meet ASME Section Xl requirements. M for continued service.. The RPV closure head is fully functional and meets B-A S
XI
. Magnetic part (MT)..alidesign bases requirementsd It isnot non-onforming or degraded.
examination of the weld.was performed per work order ei b
r e
i ng g
001 80079and identife a l r
iThe vendor calculation (0900530.303. dated 5/4/09) was performed to our surface purchase order d
10235773.has been acceptedin accordance with EN-DC-a pproximey 1inc ngt at 30 degrs.
149.Rev2. This calculation also had an independent review byWPO.T CR09-i1514 Accepted for continued service. This issue of reusing the studs has been CR 01874 VT-i Examination of ve,A by t
.discussed with our valve vendor responsible-for rebuilding the feedwater CR 01874-v-1 E-xamination. of. valve 6-CK-62A, body, to bonnet bolin fn.
n..
- (
e check valves. The studs were chased and new nuts obtained from the
".,bonnet bolting found.(3) studs and (1*),nut rejected due to B-G-2 I
I..
- warehouse.. The, new nuts run smoothly-on the chased threads and the
- hreaddamage. ThisVisual examination was-performed,-
threadur damage.Thisas isual examinationdW was5perf d
rthreads are acceptablefor reuse. There is no degradation or non-during vave
- disassembly under W 51515-0.
.conformance associated with th5e-threads in their final condition. CR09-
'1974
-Accepted for continued service.,The UT data for the Core Spray piping in.
location G
"-i4-3 has the corrosion area demonstrates thatthe remaining wall thickness is
Radiographyiofs Icoosi weld h r ciden"
" tified greater than the required nominal wall thickness. Therefore the corrosion indications (corrosion) which areunacceptable per the criteriai CF-I sc d
MS o
T ot w
x e
s-acceptable. Giventhat~this pipe hasbeen in service for the life of the peciierk yrdArM 013453 T
l n wa e plant; thecorrosion rate is low, and the minimum remaining wall.415 in is
- per work.......
o 0
- 3.
well abovenominal (vs.345 in), and no further inspections are required for icorrosion purposes.
CR09-1688 Accepted for continued service, through pipe stress analysis the minimum
- Radiography ofSIweldlocation-has identid
.wall thickness for thispipe to resist applicable stresses is.0.126". The pipe C-F-i indications (corrosion) which are unacceptable per the criteria w thickness sp.ecified.by ASME Sectin X. *This locati swale xmckness is greaterthanthe required thickness, therefore continued
.speclfiedgb AySEw -ection-XI.IS Tilocation was examined : "*
I
- operation. is acceptable. With the wear rate of 0,004 inches per year, the
- perworK order uu135 37d/wUl pipe has a remaining service life of 16.4 years. CR09-02056 j-
.Page 1 of2
FOURTH INTERVAL PNPS-NE-09-00002 Second Refueling Outage ATTACHMENT I First Period Refuel Outage 17 TABLE I TEM$ WITH FLAWS OR REEANTJN THAT REQUIRIM EVALUATI FOR Q..TINUE S...
Examination Category and Item Number Item Description Evaluation Description SI RFO17 VT-3 examination Of'SDC'loop RHR snubber H-0--Srindthatthe cld p Accepted for continued service. The snubber stroke is 6". Civil F-A setting is out of tolerance. Allowable pitco n b
Mechanical calculation M-1,192 provides Snubber Piston Rod Extension Fofsetngi tlrneAloaetolerance should be between 3 3/8 4 1/8" and our inspection found it to be at.
operability limits. So long as the snubber has room to displace during 3plant/system Heatup there is no issue. CR09-1182 3.25".
During Inservice Inspection of the GIBBs stabilizer @ azimuth F-A 225 (H-50-1-225GIBs), one (1) loosestud was identified (far Per Engineering direction the bolt was retorqued and is acceptable for right stud out of 4 studs). The inspection result is identified on -continuedservice. CR09-1996 the ISI data sheet VT-09-077 Page 2 of 2
FOURTH INTERVAL PNPS-NE-09-00002 ATTACHMENT 2 Second Refueling Outage First Period RefuelIOutage 17 TABLE 2 A
OTIIW Date '
Code Class, Item Description -Description of Work Completed RepairlReplacement Plan Number 1
Replacement Replacement bolting for.Gibbs'manway 225/270 8/20/2009 193067 Repair N9A Nozzle Overlay 8/10/2009 192 1A6 1
Replaceme'nt
-Replace bolting on the RPV N8 Nozzle Head
.8/18/2009.
179979 2
Repair Repair of Support H-10-1-12 8/7/2009 193071 2
Repair*
Repair of support H-b-1-101S 8/10/2009 190668 Page 1 of 1