ML25126A104
| ML25126A104 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/08/2025 |
| From: | Shawn Williams Plant Licensing Branch 1 |
| To: | Mcfeaters C Public Service Enterprise Group |
| Williams, S | |
| References | |
| Download: ML25126A104 (4) | |
Text
May 8, 2025 Mr. Charles V. McFeaters President and Chief Nuclear Officer PSEG Nuclear LLC - N09 P.O. Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 - CORRECTION LETTER RE: EDITORIAL ERROR WITHIN SURVEILLANCE REQUIREMENT 4.6.3.1.2.e
Dear Mr. McFeaters:
By letter dated March 19, 2007 (Agencywide Documents and Access System (ADAMS)
Accession Package No. ML070811052), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 277 to Renewed Facility Operating License No. DPR-70 for Salem Nuclear Generating Station, Unit No. 1. An editorial error was introduced in Surveillance Requirement (SR) 4.6.3.1.2.e.
In Amendment 277, SR 4.6.3.1.2.e stated:
- e.
Verifying that the Containment Pressure-Vacuum Relief Isolation valves are limited to 60% opening angle.
The previous version of SR 4.6.3.1.2.e issued on November 2, 1999 (ADAMS Accession Package No. ML993240414) stated:
- e.
Verifying that the Containment Pressure-Vacuum Relief Isolation valves are limited to 60° opening angle.
The editorial error involved the incorrect substitution of the degree symbol (°) with a percent symbol (%). This change was not requested by PSEG and was not discussed in the March 19, 2007, safety evaluation. The error was subsequently carried forward into Amendments 299 (ML110410691) and 319 (ML17165A214).
The NRC staff has concluded that the error was introduced during the preparation of the license amendment. The correction does not change any of the conclusions in the safety evaluation associated with the amendment and does not affect the associated notice to the public.
The enclosure contains the corrected technical specification page 3/4 6-13 for Subsequent Renewed License No. DPR 70.
If you have any questions, please contact me at 301-415-1009 or via email at Shawn.Williams@nrc.gov.
Sincerely,
/RA/
Shawn Williams, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-272
Enclosure:
As stated cc: Listserv
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.1.2 Each containment isolation valve shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE in accordance with the Surveillance Frequency Control Program by:
- a.
Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.
- b.
Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.
- c.
Not used.
- d.
Verifying that on a Containment Purge and Pressure-Vacuum Relief isolation test signal, each required Purge and each Pressure-Vacuum Relief valve actuates to its isolation position.
- e.
Verifying that the Containment Pressure-Vacuum Relief Isolation valves are limited to 60° opening angle.
4.6.3.1.3 In accordance with the Surveillance Frequency Control Program, verify that on a main steam isolation test signal, each main steam isolation valve actuates to its isolation position.
4.6.3.1.4 The isolation time of each power operated or automatic containment isolation valve shall be determined to be within its limit when tested pursuant to the INSERVICE TESTING PROGRAM.
4.6.3.1.5 Each required containment purge isolation valve shall be demonstrated OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after each closing of the valve, except when the valve is being used for multiple cyclings, then in accordance with the Surveillance Frequency Control Program, by verifying that when the measured leakage rate is added to the leakage rates determined pursuant to Specification 4.6.1.2.b for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60La.
4.6.3.1.6 A pressure drop test to identify excessive degradation of resilient valve seals shall be conducted on the:
- a.
Required Containment Purge Supply and Exhaust Isolation Valves in accordance with the Surveillance Frequency Control Program.
- b.
Deleted.
4.6.3.1.7 The required containment purge supply and exhaust isolation valves shall be determined closed in accordance with the Surveillance Frequency Control Program.
SALEM - UNIT 1 3/4 6-13 Amendment No. 319
ML25126A104 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL1/LA NRR/DORL/LPL1/BC NRR/DORL/LPL2-1/PM NAME SWilliams KEntz HGonzález (MMarshall for) SWilliams DATE 5/6/2025 5/6/2025 5/8/2025 5/8/2025