ML120940390

Correction to Technical Specification (TS) Page 3.3-6 for Amendment No. 188, Revise TSs to Reflect Installation of Digital GE-Hitachi Nuclear Measurement Analysis and Control Power Range Neutron Monitoring System

ML120940390
Person / Time
Site:	Grand Gulf
Issue date:	04/16/2012
From:	Wang A Plant Licensing Branch IV
To:	Entergy Operations
Wang, A B, NRR/DORL/LPLIV, 415-1445
References
TAC ME2531
Download: ML120940390 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 16, 2012 Vice President, Operations Entergy Operations, Inc.

Grand Gulf Nuclear Station P.O. Box 756 Port Gibson, MS 39150

SUBJECT:

GRAND GULF NUCLEAR STATION, UNIT 1 -ISSUANCE OF AMENDMENT RE: POWER RANGE NEUTRON MONITORING SYSTEM REPLACEMENT (TAC NO. ME2531)

Dear Sir or Madam:

On March 28, 2012, the U.S. Nuclear Regulatory Commission issued Amendment No. 188 to Facility Operating License No. NPF-49 for the Grand Gulf Nuclear Station, Unit 1 (GGNS).

which is available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML120400319. The amendment was in response to your application dated November 3,2009, as supplemented by letters dated February 8,2010, May 18, 2010, June 3, 2010, June 18, 2010, July 29,2010, September 29,2010, December 13, 2010, December 14, 2010, May 3, 2011, May 16, 2011, May 26,2011, May 31,2011, June 13, 2011, June 28,2011, July 22, 2011, September 28, 2011, October 18, 2011, October 26, 2011, November 8, 2011, and December 1, 2011.

The amendment revised the Technical Specifications (TSs) to reflect replacement of the existing Average Power Range Monitor (APRM) subsystem of the Neutron Monitoring System with a digital General Electric - Hitachi Nuclear Measurement Analysis and Control (NUMAC) Power Range Neutron Monitoring System (PRNMS). The replacement system will also change GGNS's reactor stability solution from an Enhanced Option 1-A solution to Option III, which provides an automatic instability detect-and-suppress long-term reactor core stability solution.

These changes are based on prior NRC approvals of licensing topical reports for NUMAC based PRNMS equipment and other power plant experiences when performing similar changes.

In addition, the amendment added a provision to the facility operating license that allows a monitoring period for the APRM scram Function 2.f, "OPRM [Oscillating Power Range Monitor]

Upscale," before this function's trip output to the reactor protection system trip system would be enabled. This license provision allows the limiting conditions for operation (LCOs) that would otherwise be associated with the "OPRM Upscale" Function 2.f to be deferred until the monitoring period is complete and the OPRM trip output is permanently enabled. The amendment also revised the TSs in accordance with Technical SpeCification Task Force Traveler (TSTF) TSTF-493, Revision 4, "Clarify Application of Setpoint Methodology for LSSS

[limiting safety system settings] Functions," to add surveillance footnotes in accordance with Option A of TSTF-493, Revision 4, to address instrumentation LCO issues that could occur during periodic testing and calibration of instrumentation.

- 2 By email datedApriI2.2012(ADAMSAccessionNo.ML121070139). the licensee noted it had inadvertently submitted a TS page incorrectly revising the Allowable Value in TS Table 3.3.1.1-1 (page 1 of 3), Item 2b, "Fixed Neutron Flux," to 119.3% RTP (percent rated thermal power).

The correct value is 120% RTP and this value was not changed as result of this license amendment request. This was an administrative error as this value was requested to be changed to 119.3% RTP as part of the ongoing extended power uprate (EPU) review and not the PRNMS amendment. In addition, Amendment No. 141 (used for tracking of changes on the TS pages) was left off the bottom of TS page 3.3-6 for Table 3.3.1.1-1 (page 1 of 3) and needs to be reinstated. The licensee has informed the NRC staff that it has reviewed the TS pages issued with Amendment No. 188 and found no other discrepancies.

Enclosed is the corrected TS Table 3.3.1.1-1 (page 1 of 3) for Amendment No. 188, as discussed above. These errors do not change the NRC staffs conclusions regarding this Amendment No. 188.

If you have any questions, please contact me at 301-415-1445 or via e-mail at alan.wang@nrc.gov.

Sincerely,

~ W1M~-

Alan B. Wang, Project Jlanager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-416

Enclosure:

Corrected TS Table 3.3.1.1-1 (page 1 of 3) for Amendment No. 188 cc w/encl: Distribution via Listserv

ENCLOSURE Corrected TS Table 3.3.1.1-1 (page 1 of 3)

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE

1.

Intermediate Range Monitors

a. Neutron Fl ux C High 2

3 H

SR SR SR SR

3. 3. 1. 1. 1

3. 3. 1. 1. 3 3.3.1.1.12 3.3.1.1.13

5 122/125 divisions of full scale 3

I SR SR SR SR 3.3.1.1.1

3. 3.1. 1. 4 3.3.1.1.12 3.3.1.1.13

5 122/125 divisions of full scale

b. Inop 2

3 H

SR SR 3.3. 1. 1. 3 3.3.1.1.13 NA 3

I SR SR 3.3.1. 1. 4 3.3.1.1.13 NA

2.

Average Power Range Monitors

a. Neutron Setdown Flux High, 2

3 (cl H

SR SR SR SR 3.3.1.1.7 3.3.1. 1. 10 (dl (e) 3.3.1.1. 19 3.3.1.1.20

5 20% RTP

b. Fixed Neutron Flux -High 1

3(cl G

SR SR SR SR SR 3.3.1.1.2 3.3.1.1.7 3.3.1.1.10(d) (e) 3.3.1.1.19 3.3.1.1.20

5 120% RTP

c. Inop 1,2 3 (cl H

SR 3.3.1.1.20 NA

d. Flow Biased Simulated Thermal Power -

High 1

3(c)

G SR SR SR SR SR SR 3.3.1.1.2 3.3.1.1.7 3.3.1.1.10(d) (e) 3.3.1.1.17 3.3.1.1.19 3.3.1.1.20 (b)

e. 2-0ut-Of-4 Voter 1,2 2

H SR SR SR SR 3.3.1.1.19 3.3.1.1.20 3.3.1. 1. 21 3.3.1. 1. 22 NA

f. OPRM Upscale

~ 24% RTP 3 (cl J

SR SR SR SR SR 3.3.1.1.7 3.3.1.1.10(dl (e) 3.3.1.1.19 3.3.1.1.20 3.3.1.1.23 (f)

(continued)

GRAND GULF 3.3-6 Amendment No. t4+/-, ~, 188

- 2 By email datedApriI2.2012(ADAMSAccessionNo.ML121070139), the licensee noted it had inadvertently submitted a TS page incorrectly revising the Allowable Value in TS Table 3.3.1.1-1 (page 1 of 3), Item 2b, "Fixed Neutron Flux," to 119.3% RTP (percent rated thermal power).

The correct value is 120% RTP and this value was not changed as result of this license amendment request. This was an administrative error as this value was requested to be changed to 119.3% RTP as part of the ongoing extended power uprate (EPU) review and not the PRNMS amendment. In addition, Amendment No. 141 (used for tracking of changes on the TS pages) was left off the bottom of TS page 3.3-6 for Table 3.3.1.1-1 (page 1 of 3) and needs to be reinstated. The licensee has informed the NRC staff that it has reviewed the TS pages issued with Amendment No. 188 and found no other discrepancies.

Enclosed is the corrected TS Table 3.3.1.1-1 (page 1 of 3) for Amendment No. 188, as discussed above. These errors do not change the NRC staffs conclusions regarding this Amendment No. 188.

If you have any questions, please contact me at 301-415-1445 or via e-mail at alan.wang@nrc.gov.

Docket No. 50-416

Enclosure:

Corrected TS Table 3.3.1.1-1 (page 1 of 3) for Amendment No. 188 cc w/encl: Distribution via Listserv DISTRIBUTION:

PUBLIC LPL4 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrDeEicb Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl4 Resource RidsNrrDraAhpb Resource RidsNrrDssSrxb Resource Sincerely, IRA!

Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrDssStsb Resource RidsNrrLAJBurkhardt Resource RidsNrrPMGrandGulf Resource RidsOgcRp Resource RidsRgn4MailCenter Resource BDittman, NRRIDE/EICB GLapinsky, NRRIDRA!AHPB KBucholtz, NRR/DSS/STSB ADAMS Accession No ML120940390 OFFICE NRRlLPL4/PM NRRlLPL4/LA INRR/LPL4/BC NRR/LPL4/PM NAME AWang JBurkhardt MMarkley AWang DATE 4/16/12 4/10/12 4/13/12 4/16/12 OFFICIAL AGENCY RECORD