ML17086A162
| ML17086A162 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 04/09/2017 |
| From: | John Lamb Special Projects and Process Branch |
| To: | Dent J Entergy Nuclear Operations |
| Lamb, John, NRR/DORL/LSPB | |
| References | |
| CAC ME3253 | |
| Download: ML17086A162 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. John Dent, Jr.
Site Vice President Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508 April 9, 2017
SUBJECT:
PILGRIM NUCLEAR POWER STATION - CORRECTION TO TECHNICAL SPECIFICATION PAGE 5.0-11 (CAC NO. ME3253)
Dear Mr. Dent:
By letter dated January 27, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17018A199), the U.S. Nuclear Regulatory Commission (NRC) issued a correction to address typographical errors in Technical Specification (TS) page 5.0-11.
As background, by letter dated January 26, 2011 (ADAMS Accession No. ML110050298), the NRC issued Amendment No. 234 to Facility Operating License No. DPR-35 for the Pilgrim Nuclear Power Station (PNPS). This amendment consisted of changes to the TSs in response to Entergy Nuclear Operations, Inc. 's (Entergy's) application dated January 24, 2010, as supplemented by letters dated September 7, 2010, and November 4, 2010. The amendment revised TSs Sections 1.0, 3.6, 3.6.A, and 5.5 to include reference to the pressure and temperature limits report.
By letter dated November 26, 2008 (ADAMS Accession No. ML081570366), the NRC issued Amendment No. 231 to Facility Operating License No. DPR-35 for PNPS. This amendment consisted of changes to the TSs in response to Entergy's application dated November 29, 2007.
The amendment revised TS Sections 3.7.B.2 and 5.5 related to control room habitability.
Subsequent to the issuance of the January 27, 2017, correction letter, the NRC staff identified typographical errors in the revised TS page 5.0-11 (for Amendment No. 234), which were inadvertently introduced when staff revised this TS page. In TS Section 5.5.8.d, the Main Control Room Heating, Ventilation and Air Conditioning System and the Ventilation Filter Testing Program should be spelled out instead of the acronym only usage.
Enclosed is the revised TS page 5.0-11 (for Amendment No. 234). We apologize for any inconvenience.
If you have any questions, please contact me at 301-415-3100 or John.Lamb@nrc.gov.
Docket No. 50-293
Enclosure:
Revised TS page 5.0-11 (for Amendment No. 234) cc w/encl: Distribution via Listserv
'"""1111v*--'* Lamb, Senior Project Manager cial Projects and Process Branch vision of Operating Reactor Licensing ffice of Nuclear Reactor Regulation
ENCLOSURE Revised TS page 5.0-11 (for Amendment No. 234)
5.5 Programs and Manuals Programs and Manuals 5.5
- d.
- e.
- f.
5.5.9 "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors,"
Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.
Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one subsystem of the Main Control Room Heating, Ventilation and Air Conditioning System, operating at the flow rate required by the Ventilation Filter Testing Program, at a Frequency of 24 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 24 month assessment of the CRE boundary.
The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of OBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.
Each Surveillance Requirement shall be performed within the specified SURVEILLANCE INTERVAL with a maximum allowable extension not to exceed 25 percent of the specified SURVEILLANCE INTERVAL. The SURVEILLANCE INTERVAL requirement is applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.
Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
- a.
RCS pressure and temperature limits for heatup, cool-down, low temperature operation criticality and hydrostatic testing as well as heatup and cool-down rates shall be established and documented in the PTLR for the following:
i)
Limiting conditions for Operation Section 3.6.A.2
- b.
The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the following document:
i)
SIR-05-044-A "Pressure-Temperature Limits Report Methodology for Boiling Water Reactors", April 2007
- c.
The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any reason or supplement thereto.
(continued)
Amendment No. ~. 234 5.0-11
ML17086A162 OFFICE NRR/DORL/LSPB/PM NRR/DORL/LPL 1/LA NRR/DORL/LSPB/BC NAME JLamb LRonewicz DBroaddus DATE 03/28/2017 03/28/2017 04/02/2017