ML15237A258

Pilgrim - Refueling Outage (RFO)-20, In-Service Inspection (ISI) Owners Activity Report (OAR-1) Submittal

ML15237A258
Person / Time
Site:	Pilgrim
Issue date:	08/20/2015
From:	Perkins E P Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2.15.060
Download: ML15237A258 (6)

Text

SEn tergy Entergy Nuclear Operations, Inc, Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 August 20, 2015 U.S. Nu~clear Regulatory Commission ATTFN: Document Control Desk Washington, -DC 20555-0001

SUBJECT:

Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power Station Docket No. 50-293 License No. DPR-35 Pilgrim Refueling Outage (RFO)-20 In-Service Inspection (ISI) Owners Activity Report (OAR-I) Submittal LETTER NUMBER: 2.15.060

Dear Sir or Madam:

By this letter Entergy submits to the NRC the attached Pilgrim Nuclear Power Station (PNPS)In-Service Inspection (ISI) Owners Activity Report (OAR-I) for Operating Cycle 20.This report has been prepared in accordance with ASME Section XI 2001 with 2003 addenda and NRC approved Code Case N-532-5, and has been certified by the Authorized Nuclear Inservice Inspector (AN II) attesting that all code-required examinations and repair/replacement activities at PNPS during Cycle 20 were performed in accordance with the requirements of the ASME XI Code.There are no new commitments made in this letter.If you have any questions regarding the information contained in this letter, please contact me at (508) 830-8323 or Murray Williams at (508) 830-8275.Sincerely, Everett P. (Chip) Perkins, 'r.Regulatory Assurance Manager EPP/mw

Attachment:

Engineering Report No. PNpS-RPT-15-00003, Rev. 0"PNPS Owners Activity Report (OAR-I) for Cycle 20" (3 pages)

Letter Number: 2.15.060 Page 2 of 2 cc: Mr. Richard Guzman, Project Manager Office of Nuclear Reactor Regulation Mail Stop: 0-802 U.S. Nuclear Regulatory Commission 1 White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Daniel H. Dorman Regional Administrator, Region I U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd., Suite 100 King of Prussia, PA 19406-1 415 NRC Senior Resident Inspector Pilgrim Nuclear Power Station Attachment To PNPS Letter 2.15.060 Engineering Report No. PNPS-RPT-15-00003, Rev. 0"PNPS Owners Activity Report (OAR-I) for Cycle 20" (3 pages)

FOURTH INTERVAL PNPS-RPT-1 5-00003 THIRD PERIOD REFUEL OUTAGE 20 ATTACHMENT

9.1 ENGINEERING

REPORT COVER SHEET & INSTRUCTIONS Engineering Report No. PNPS-RPT-I15-00003 Rev 0 Page 1 of 3 ENTERGY NUCLEAR Engineering Report Cover Sheet Engineering Report Title: PNPS ACTIVITY REPORT (OAR-I) FOR CYCLE 20 Engineering Report Type:.New []Revision LI Cancelled LI Superseded Superseded by: LI Applicable Site(s)AuNOI LI ANO2 LI LI 1P3 LI ECH LI JAF GGNS LI PNPS[] RBS LI VY LI WF3 []wpo LI PLP LI EC No. N/_AA RepOrt Origin:[] Entergy LI Vendor Vendor Document No.: N/A Quality-Related:

[] Yes[] No R. Pardee / Prepared by: Reviewed by: Approved by: Approved by: Date: Responsible Engineer (Print Naine/Sign)

K. Bienvenue

/ K- t41kL Date: Reviewer (Print Name/Sign)

Elizabeth York (HSB) ~

ANII (Print Name/Sign)

Supervisor

/ Manager (Print Name/Sign)

_:29z-/:-7-2q -I page 1 of 3 page of 3EN-DC-i147 Rev.6 FOURTH INTERVAL PN PS-RPT-1 5-00003 THIRD PERIOD REFUEL OUTAGE 20 FORM OAR-I OWNERS ACTIVITY REPORT Report Number PNPS-RPT-1 5-00003 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 20 Current Inspection Interval-(1st, 2nd, 3rd, 4th, Other)Current Inspection Period (1st, 2nd, 3rd)th 4 3rd Edition and Addenda of Section XI applicable to the Inspection Plan 1998 Edition, 2000 Addi Date and Revision of Inspection Plan: PNPS ISI Proaqram Plan. No. SEP-ISI-PNPS-001 Rev.3 Edition and Addenda of ASME Section Xl applicable to Repairs and Replacements, if different than the Inspection Plan 2001 Edition. 2003 Addenda enda Code Cases used for inspection and evaluation:

N-51 3-4, N-71 6, N-702 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 RFO20 conform to the requirements of Section XI.Signed R. Pardee / Sr Engineer Owner or Owner' s designee, Title Date -. -/CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by HSB Global Standards have inspected the components described in this Owners Activity 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 Xl.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 loss of any kind arising from or connected with this inspection.

Commisin 'p/ --Date / National Board, State, Provi'nce, and Edndorsements Date 0 ~page 2 of 3 EN-DC-147 Rev.6 page 2 of 3 EN-DC-147 Rev.6 FOURTH INTERVAL PNPS-RPT-1 5-00003 THIRD PERIOD REFUEL OUTAGE 20 TABLE 1 ITrEMS wrlTH FLAWS OR RELEVANT THAT REQUIRED EVALUATI[ON FOR CONTI[NUED SERVICE Examination Category and Item Number Itern Description Evaluation Description D-B 1 D2.10 Salt Service Water pipe spool JF2g-8-4 thru-wall Through-wall leakage of carbon steel service water pipe spool due leakage to localized degradation of internal rubber lining was evaluated and determined operable but degraded/nonconforming with compensatory measures (CR-PNP-2014-081 5). The leakage was determined to be a housekeeping concern only as the leak was located downstream of the RBCCW and TBCCW heat exchangers and therefore did not impact the ability of the Salt Service Water system to perform its safety function.

The flaw was evaluated using methodology detailed in Code Case N-5I13-4 and was submitted for NRC approval in relief request PRR-25 (Entergy letter 2.14.023 dated 3/5/14). The condition was corrected in May 2014 during a_______________lant shutdown when the spool was replaced.E-A I El .11 IWE General Visual Walkdown areas of Primary containment determined to be operable with the degraded degraded primary containment coatings conditions accepted for continued service with continued monitoring.

Debris loading for ECCS suction strainers was evaluated and determined to be acceptable based on actual weight of debris (flaking paint) compared to design allowable limits (CR-_____________________________________________PNP-201 5-4375).TABLE 2 ABSTRACT OF REPAIRIREPLACEMENT ACTIVITIES REQUI[RED FOR CONTI[NUED SERVICE Code Class I[tem Description Date RepairlReplacement

______ Description Of Work Completed Plan Number 3 Replacement Salt Service Water pipe spool JF2g-8-4 5/16114 375247-06_________

_____________replaced

______1 Replacement Feedwater check valve 6-CK-62A hinge 5117/14 365394-02

& 365394-18_________

_____________pin covers replaced______

I Replacement RPV washers at stud locations 23, 24 & 5/19/15 413547-01_____ ____ ____ _____ ____ 43.__ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _page 3 of 3 page of 3EN-DC-147 Rev.6