ML16363A266

Correction to Amendment No. 234 Change in Technical Specification Measurement Frequency from 18 Months to 24 Months

ML16363A266
Person / Time
Site:	Pilgrim
Issue date:	01/10/2017
From:	Booma Venkataraman Plant Licensing Branch 1
To:	Dent J Entergy Nuclear Operations
Ventkataraman, B, DORL/LPLI, 415-2934
References
CAC ME3253
Download: ML16363A266 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 10, 2017 Mr. John Dent, Jr.

Site Vice President Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508

SUBJECT:

PILGRIM NUCLEAR POWER STATION - CORRECTION TO AMENDMENT NO. 234 RE: CHANGE IN TECHNICAL SPECIFICATION MEASUREMENT FREQUENCY FROM 18 MONTHS to 24 MONTHS (CAC NO. ME3253)

Dear Mr. Dent:

By letter dated January 26, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110050298), the U.S. Nuclear Regulatory Commission issued Amendment No. 234 to Facility Operating License No. DPR-35 for the Pilgrim Nuclear Power Station (Pilgrim). This amendment consisted of changes to the technical specifications (TSs) in response to Entergy Nuclear Operations, lnc.'s (the licensee) application dated January 24, 2010, as supplemented by letters dated September 7, 2010, and November 4, 2010 (ADAMS Accession Nos. ML100270054, ML102580240, and ML103200208, respectively).

The amendment revised TSs Section 1.0, "Definitions"; TS Section 3.6, "Primary System Boundary"; Specification 3.6.A, "Thermal and Pressurization Limitations"; and TS 5.5, "Programs and Manuals," to include reference to the Pressure and Temperature Limits Report.

Subsequent to issuance of the amendment, typographical errors were discovered on TS page 5.0-11 of the amendment. In TS Section 5.5.8.d, the periodic measurement frequency of the control room envelope (CRE) pressure was to be 24 months instead of 18 months. TS Section 5.5.8.d was to read, " ... 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 measurement frequency of 24 months was approved in Amendment No. 231 (ADAMS Accession No. ML081570366), dated November 20, 2008. However, the licensee inadvertently submitted the marked up and camera ready page in the license application for Amendment No. 234 without incorporating changes to TS Section 5.5.8.d from Amendment No. 231. This error was carried forward in Amendment No. 234.

J. Dent, Jr. Enclosed is the revised TS page 5.0-11 for Amendment No. 234.

If you have any questions, please contact me at 301-415-2934 or by e-mail to Booma.Venkataraman@nrc.gov.

Sincerely,

~.2o~~

Booma Venkataraman, Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293

Enclosure:

Revised TS page 5.0-11 for Amendment No. 234 cc w/encl: Distribution via Listserv

ENCLOSURE Revised TS page 5.0-11 for Amendment No. 234

Programs and Manuals 5.5 Programs and Manuals 5.5 "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.

d. 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 MCREC System, operating at the flow rate required by the VFTP, at a Frequency of 24 months on a STAGGERED TEST BASIS. The results shall be treated and used as Part of the 24 month assessment of the CRE boundary.

e. 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 DBA 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.

f. 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.

5.5.9 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 NRG, 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 NRG upon issuance for each reactor vessel fluence period and for any reason or supplement thereto.

(continued)

Amendment No. ~. 234 5.0-11

ML16363A266 OFFICE NRR/DORL/LPL 1/PM NRR/DORL/LPL 1/LA NRR/DORL/LPL 1/BC(A) NRR/DORL/LPL 1/PM NAME BVenkataraman LRonewicz SKoenick BVenkataraman DATE 1/05/2017 1/05/2017 1/10/2017 1/10/2017