ML11235A729
| ML11235A729 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 07/27/2011 |
| From: | Bethay S Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2.11.049 | |
| Download: ML11235A729 (8) | |
Text
"v En tergy--
Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 Stephen J. Bethay Director, Nuclear Safety Assurance July 27, 2011 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 2055
SUBJECT:
Entergy Nuclear Operations, Inc Pilgrim Nuclear Power Station Docket No. 50-293 License No. DPR-35 Pilgrim Refueling Outage (RFO)-18 In-Service Inspection (ISI) Owner's Activity Report (OAR-i) Submittal LETTER NUMBER:
2.11.049
Dear Sir or Madam,
By this letter Entergy submits to the NRC the attached Pilgrim Nuclear Power Station In-Service Inspection (ISI) Owner's Activity Report (OAR-i) for Operating Cycle 18 in accordance with ASME Section XI and NRC-approved Code Case N-532-4. PNPS is in the second period of the 4 th ISI Interval.
The report contains a tabulation of all in-service examinations and Code repair/replacement activities performed at Pilgrim Station for the beginning of Operating Cycle 18 through the end of Refueling Outage 18. The attached report is required to be submitted to NRC within 90 days of the last inspections.
Copies of the examination of vendor reports and data sheets are retained at Pilgrim Station for NRC review, if required.
The Pilgrim ISI Program conforms to the 1998 through 2000 addenda of the ASME Section Xl code. ISI-related activities associated with repair/replacements, NDE and pressure testing, however, is performed in accordance with the 2001 edition through 2003 addenda of ASME Section XI in accordance with NRC-approved relief request ISI-2008-1 (TAC No. ME0238).
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, Step thJ jay Director, Nuclear Safety ssurance
Attachment:
PNPS Owners Activity Report (OAR) for the Second Period of the 4 th Interval, Engineering Report No. PNPS-RPT-11-00003, Rev. 0 (5 pages)
Atý -ý 49
Entergy Nuclear Operations, Inc.
Entergy Letter No. 2.11.049 Pilgrim Nuclear Power Station Page 2 of 2 cc:
Mr. Richard Guzman, 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 Regional Administrator U. S. NRC, Region 1 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector Pilgrim Nuclear Power Station
Attachment to Entergy Letter No. 2.11.049 PNPS Owner's Activity Report (OAR-i) for the Second Period of the 4th Interval (5 Dages)
ATTACHMENT 9.1 SHEET 1.OF I ENGINEERING REPORT COVER SHEET isEn Engineering Report No. 'PNPS-RPT-11-00003 F
Page 1
of Attachment I pages: 1-2 pages: I tewgy ENTERGY NUCLEAR Engineering Report Cover Sheet Engineering Report
Title:
PNPS OWNERS ACTIVITY REPORT (OAR) FOR THE SECOND PERIOD OF THE 4TH INTERVAL
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FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number PNPS-RPT-11-00003 Plant Plgrim Nuclear Power Station Unit No.
1 Commercial Service Date June 8, 1972 Refueling Outage Number 18 (If applicable)
Current Inspection Interval 4th (I", 2n, 3", 4", other)
Current Inspection Period 2 nd (1=i, 26, 3" )
Edition and Addenda of Section XI applicable to the Inspection Plans 1998 Edition, 2000 Addenda Date / Revision of Inspection Plans PNPS ISI Program Plan, No. PNPS-RPT-05-001 Rev. 1 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans 2001 Edition, 2003 Addenda Code Cases used:
Reference PNPS ISI Program Plan, No. 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 18 conform to the requirem Sentbo XI (refueling outage number)
Signed Date
"_________--__ I (owner or Owneil'sdesignee. 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 Owner's Activity Report, and state that to the best of my knowledge and belief, the Owner has performed all 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 evaluatio escribed in this report. Furthermore, neither the Inspector nor his employer shall be liable in any inj damage or a loss of any kind arising from or connected with this inspection
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National Board, State, Province, and Endorsements Date
FOURTHINTERVAL PNPS-RPT-11-00003 ATTACHMENT 1 Second Period Refuel Outage 18 TABLE 1 ITEMSWITH: FLA WOR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED.S*E ICE Examination Category and Item Number Item Description Evaluation Description While performing ISI inspections on Torus Saddle Supports in Accepted for continued service. The degraded grout conditions are F-A IBays 1-5 degraded cosmetic grout conditions adjacent to the outside the baseplate footprint and therefore are not part of the structural Ftorus saddle support base plates was noted. There was also load path and any cracking or spalling is non-structural and cosmetic only.
some minor cracking in the concrete pedestal for the support. Therefore these conditions will not adversely affect the structural load These conditions are cosmetic in nature.
carrying capacity of the Torus Saddle Supports.
ISI VT-3 Exam on Anchor H-10-1-87SA in the A' RHR Quad Accepted for continued service. Cracks identified in this condition report F-A was performed and it does not meet acceptance criteria of are cosmetic in nature and do not exhibit signs that the cracks are due to CEP-NDE-0903. There is a small crack in the concrete significant stress or overload. These cracks do not adversely affect adjacent to the anchor on the wall.
operability of the H-10-1-87A support.
ISI VT-3 Exam on Lateral Restraint H-10-1-21SR in the A Accepted for continued service. Identified conditions affecting support H-RHR Quad was performed and it does not meet acceptance 10-1 -21 SR are minor. Angular misalignment is acceptable, non of the F-A criteria of CEP-NDE-0903. The Spherical bearings do not identified discrepancies adversely affects the structural integrity of the move and there is a 7% misalignment of the strut. This ident. Screpancie S
ise ly OPEcts the associate condition was previously identified by NCR 91-137, reworked support. Support H-10-1-21SR is fully OPERABLE as is the associated and accepted.
loop of RHR.
RPV stud thread damage to 24 studs occurred during head Accepted for continued service. 23 studs were repaired and or accepted B-G-1 removal, several vessel studs received damage to the upper as is, RPV number one stud replaced and preservice UT completed.
portion of the stud threads.
I __________________
J Page 1 of 2
FOURTH INTERVAL PNPS-RPT-11-00003 ATTACHMENT I Second Period Refuel Outage 18 TABLE 1 ITEMS.WITH FLAWS OR RELEVANT CONDITIONS. THAT REQUIREb EVALUATION FOR CONTIUED;SERVICE.......
Examination Category and Item Number Item Description Evaluation Description During the visual VT-1 examination of the RPV Closure Head Washers at stud locations 19 through 36 (RPV-CW-19-36) linear indications were recorded on the bottom (flat) surface of washers 19 and 22. A previous (2001) historical acceptable indication in washer 30 was also recorded with no changes.
During the expanded scope VT-i examinations of the RPV Accepted for continued service. The indications are not fatigue or Closuringthe Hexpandd W
shpers an ai nalsix s
() w hers #s 5 stress corrosion cracks and therefore are not expected to grow during B-G-1 14, 16, 18, 39 47) were identified with linear indications that future operation. There are no operational concerns from the identified did not meet ASME Seeidentionedwithlinearicdieaacceptanceindications associated with the continued permanent use of the washers did not meet ASME Section X1 IWB-3515.1 code acceptance idniidinteCFs standards. Linear indications on two (2) washers (#'s 19 22) identified in the ONE's.
was previously reported in CR-PNP-2011-01907. VT-I examination have been completed on all RPV Closure Head Washers and a total of eight (8) washers have been identified with linear indications.
During ISI inspection of the IWE-LINERDRAINS on 74' RB, Drain line 1 was leaking approximately 100 drops per minute. Accepted for continued service. Small amounts of leakage from SFP E-C Drain line 1 is the discharge at the funnel at the north wall of leakage detection system is not an operability or functionality concern.
the spent fuel pool and it drains the fuel pool liner monitoring Continued monitoring and trending is the appropriate response to trench drain.
variations in the observed leakage.
An ASME Section Xl IWE General Visual Examination was conducted of the condition of the Drywell and Torus interiors and exterior surfaces during RFO-18 per PNPS Procedure Accepted for continued service. No repair is recommended to be E-A 2.1.8.7. Various "relevant conditions" exceeding the completed this outage. Development of a systematic approach is acceptance criteria in Engineering Procedure CEP-CII-003 recommended for future repair of coatings in the drywell and to the torus.
were found, mainly related to protective coating condition. -
Reference CR07-2093 from RFO16 to compare results.
During RFO18 ISI VT-3 exam on H-2-1-SS21 Snubber, the Accepted for continued service. No Degraded or Nonconforming F-A cold piston rod setting was 4 1/4" and it should have been 3 Condition exists, affected snubber (SS-02-20-21) listed in this CR 5/16" to 4" per PNPS 3.4-28 and CEP-NDE-0903 for the as supports recirc piping in the drywell. Snubber piston rod setting evaluated left.
by engineering and found acceptable.
Page 2 of 2
FOURTH INTERVAL PNPS-RPT-11-00003 ATTACHMENT 2 Second Period Refuel Outage 18 TABLE 2
- ABSTRACT OF REPAIRIREPLACEMENT ACTIVmýE:REQUIRED FOR CONTINUED SERVICE Date Code Class Item Description Description of Work Completed RepairlReplacement Plan Number 2
Replacement Restore RHR support H-10-1 -186 2/1/11 247126-21 3
Repair Repair broken weld on SSW support H-29-1-2 5/24/11 274898 1
Replacement Replace FW Check Valve 62A bolting 4/28/11 52253926 1
Replacement Replace RPV Closure Head Stud #1 in RFO18 5/9/11 274101 1
Replacement Replace galled 2" RPV head vent piping flange bolting 5/9/11 274012 Page 1 of 1