ML023180558
| ML023180558 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/04/2002 |
| From: | John Carlin Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BL-02-002, LR-N02-0369 | |
| Download: ML023180558 (4) | |
Text
PSEG Nuclear LLC P 0 Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG Nuclear LLC NOV 0 4 Z00Z LR-N02-0369 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
RESPONSE TO NRC BULLETIN 2002-02 REACTOR PRESSURE VESSEL HEAD AND VESSEL HEAD PENETRATION NOZZLE INSPECTION PROGRAMS SALEM GENERATING STATION UNIT I FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Bulletin 2002-02, "Reactor Pressure Vessel Head And Vessel Head Penetration Nozzle Inspection Programs," requires operators of pressurized-water reactors (PWRs) to submit examination results within 30 days after plant restart following the next inspection of the reactor pressure vessel head:
The results of our examination are provided in Attachment 1 to this letter. Should you have any questions regarding this response, please contact Michael Mosier at (856) 339 5434.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on+/-'X' 2~.1-2-
Since relyy Jo Carlin c President Nuclear Reliability Attachment 95-2168 REV. 7/99
Document Control Desk NOV 0 4 2002 LR-N02-0369 C:
Mr. H. J. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Fretz, Project Manager - Salem U. S. Nuclear Regulatory Commission Mail Stop 08B2 Washington, DC 20555 USNRC Senior Resident Inspector-Salem (X24)
Mr. K Tosch, Manager IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625 2
Document Control Desk LR-N02-0369
- 1. Within 30 days after plant restart following the next inspection of the RPV head and VHP nozzles to identify the presence of any degradation, all PWR addressees are requested to provide:
A.
The inspection scope and results, including the location, size, extent, and nature of any degradation (e.g. cracking, leakage, and wastage) that was detected; details of the NDE used (i.e., method, number, type, and frequency of transducers or transducer packages, essential variables, equipment, procedure and personnel qualification requirements, including personnel pass/fail criteria); and criteria used to determine whether an indication, "shadow," or "backwall" anomaly is acceptable or rejectable.
B.
The corrective actions taken and the root cause determinations for any degradation found.
PSEG RESPONSE:
During the Salem Unit I refueling outage (1 R1 5) October 2002, a planned 100%
bare-metal visual (BMV) examination of the reactor pressure vessel head was performed to inspect for any indication of boric acid deposits. This inspection was performed in accordance with commitments contained in our letter dated September 6, 2002 (LR-N02-0297) NRC Bulletin 2002-02.
To facilitate the examination, the reflective mirror insulation was completely removed from the reactor pressure vessel head, providing a 360-degree, 100%
visual access to all penetrations including the head vent. The inspection was not inhibited or masked by the presence of insulation, any deposits or debris or other factors that could interfere with the detection of boric acid leakage; therefore, the capability of detecting and discriminating small amounts of boric acid deposits, if present, was afforded to the certified examiners.
The intersections of 100% of each nozzle and the head vent were easily observed 360 degrees and there was no indication of the presence of boric acid deposits. The intersections between the Control Rod Drive Mechanism (CRDM) nozzles and the reactor head were well defined and clean of any indication of boric acid deposits that have taken the physical appearance of "popcorn" or evidence of any boric acid crystal growth extruding up from the head, on the outside surface of the CRDM nozzle. There was no evidence of boric acid leakage from sources above the head, such as canopy seal welds that could leak downward onto the head.
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Document Control Desk Attachment I LR-N02-0369 Residual dye penetrant developer about selected canopy seal welds was reviewed against pfeVi -us historical photographs and again was evaluated as no indication of reactor coolant system leakage.
In summary, a 100% BMV examination of the Salem Unit 1 reactor pressure head was performed during 1 R1 5, October 2002. There was no evidence of boric acid leakage detected.
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