LR-N25-0082, In-Service Inspection Activities
| ML25267A058 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/23/2025 |
| From: | Desanctis R Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N25-0082, N-532-5 | |
| Download: ML25267A058 (1) | |
Text
Richard Desanctis, Jr.
Plant Manager - Salem, PSEG Nuclear PO Box 236 Hancocks Bridge, New Jersey 08038-0236 856-339-1060 Richard.DeSanctisJr@pseg.com LR-N25-0082 September 23, 2025 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555-0001 Salem Generating Station Unit 1 o PSEG I NUCLEAR ASME Code Case N-532-5 Renewed Facility Operating License DPR-70 NRC Docket No. 50-272
Subject:
In-Service Inspection Activities This letter submits the Owner's Activity Report for In-Service Inspection (ISi) activities conducted at the Salem Generating Station Unit 1 during the thirtieth refueling outage.
This report is submitted in accordance with Code Case N-532-5 "Repair/Replacement Activity Documentation Requirements and In-Service Summary Report Preparation and Submission Section XI, Division 1". to this letter contains the required Salem Unit 1 Owner's Activity Report.
There are no commitments contained in this letter.
Should you have any questions regarding this submittal, please contact Ms. Bernadette Humphrey at Bernadette.Humphrey@pseg.com Sincerely, Richard Desanctis, Jr.
Plant Manager - Salem
September 23, 2025 Page 2 LR-N25-0082 - Salem Unit 1 Owner's Activity Report - S1 R30 cc:
USN RC - Administrator - Region 1 USN RC - Licensing Project Manager - Salem USN RC Senior Resident Inspector - Salem NJDEP, Bureau of Nuclear Engineering Corporate Commitment Coordinator - PSEG ASME Code Case N-532-5 Salem Unit 1 Owner's Activity Report-S1 R30 (2 Pages)
FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number =S~1~R=3=0~--------------------------------
Plant Salem Generating stat;on Unit No. ---~1 ____ Commercial Service Date July 1. 1977 Refueling Outage no. ____
.....:.3.a.O __ _
(tf applicable)
Current Jnspectlon Interval ISi - Fifth (5th), Cl Sf - Third (3rd )
(lat. 2nd, 3nl, 4'11, -I Current Inspection Period ISi - Second (Z"d) CISI - Second (2nd)
(ht bl. 3rd)
Edition and Addenda of Section XI Applicable to the Inspection Plans 2013 Edition, No Addenda Date and Revision of Inspection Plans IsI,cIsn Revision 6 September 2024 Edition and Addenda of Section XI Applicable to Repair/Replacement Activities, if different than the Inspection Plans __ _
Same as ISi (CIS~ Plan Code Cases used for Inspection and evaluation: N-532-5, N-716-1, N-729-6 CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are eorrect; (bl the examinations and tesls meet the Inspection Plan as required by the ASME Code,Section XI; and (c) the repair/replacement actiVIHes and evaluations supporting the completion of S1R30 Conform to the requirements of Section XI.
<R.._10* outaa* num*..-1 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 Hartford steam Boiler Inspection and lnsurance Company of Hartford. Connecticut have Inspected the items described in this OWner'sActivity Report, and state that, to the best of my knowledge anct belief, the owner has performed all actiVities represented by this report in accordance with the requremerts of Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement actlvilles and evaluatio ribed in this roport. Furthermore, neither the Inspector nor his employer shall be liable in any ma~perty damage or a loss of any kind arising from or conne~ed with this Inspection.
Taylor Rash
/
Commission NB17603 and N. I. R lrtSPecf:;;;!s Sgnature (Nadonal BDald Nurat>e, and Endo!"Hment)
Date q / I 8 ) 2.02, t;"
FORM OAR-1 OWNER'S ACTIVITY REPORT Exam Category A-E TABLE1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Item Item Description Evaluation Description Number MRP-227A Reactor Vessel Core Barrel Evaluation was performed under order degradation, spec1f1cally Four 80139035-0030 for one (1) cycle operation.
(4) failed Thermal Shield Support Block Bolts, Two (2) at AZ 292 (previously removed In S1R29) and Two (2) TSSB Bolts at AZ 247 have UT Indications Four (4)
Flexure Bolts failed and found on lower Core Plate, J9 Fuel Pin broke off and Upper Girth Weld had 1nd1catIons, Boat Sample removed for analysis.
TABLE2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Item Description of Work Date Repair/Replacement Code Class Description Complete Plan Number none none none none none