GNRO-2012/00024, Supplemental Information Extended Power Uprate

Supplemental Information Extended Power Uprate

ML12109A308
Person / Time
Site:	Grand Gulf
Issue date:	04/18/2012
From:	Krupa M Entergy Corp, Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2012/00024
Download: ML12109A308 (10)

Text

Entergy Operations, Inc.

P. O. Box 756 Port Gibson, MS 39150 Michael A. Krupa Director, Extended Power Uprate Grand Gulf Nuclear Station Tel. (601) 437-6684 GNRO-2012/00024 April 18, 2012 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

Supplemental Information Extended Power Uprate Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29

REFERENCES:

1. Entergy Operations, Inc. letter to the NRC (GNRO-2010/00056),

License Amendment Request - Extended Power Uprate, September 8, 2010 (ADAMS Accession No. ML102660403)

2. NRC letter to Entergy Operations, Inc. dated March 28, 2012, Grand Gulf Nuclear Station, Unit 1 - Issuance of Amendment Re: Power Range Neutron Monitoring System Replacement (TAC NO. ME2531)

(Amendment 188)

Dear Sir or Madam:

Entergy submitted a license amendment request (LAR) for an extended power uprate (EPU) for Grand Gulf Nuclear Station, Unit 1 (GGNS) in Reference 1. The mark-up of the Technical Specification (TS) pages included in the EPU LAR was based on the then current GGNS TSs and acknowledged that certain pages were affected by changes addressed in the proposed GGNS Power Range Neutron Monitoring System (PRNMS) LAR, which was under review at the time. Based on the recent issuance of Amendment 188 for the PRNMS (Reference 2), an update of the EPU TS mark-up for certain pages affected by the PRNMS LAR is required. provides the revised marked up pages.

This is an administrative change. Based on the approved PRNMS LAR, the revised EPU TS mark-up reflects the re-alignment of text on certain pages, includes a revision to the page numbering associated with TS Table 3.3.1.1-1, adds the title on the page 2 of Table 3.3.1.1-1, and corrects a typographical error in Function 1.a., Neutron Flux C High of Table 3.3.1.1-1 replacing C with a hyphen. No changes to the technical content originally proposed in the EPU LAR TS mark-ups are proposed.

GNRO-2012/00024 Page 2 of 2 No change is needed to the no significant hazards consideration included in the initial LAR (Reference 1) as a result of the administrative revision to certain pages of the TS mark-up.

There are no new commitments in this letter.

If you have any questions or require additional information, please contact Jerry Burford at 601-368-5755.

I declare under penalty of perjury that the foregoing is true and correct. Executed on April 18, 2012.

Sincerely, MAK/FGB Attachments:

1. Revised Technical Specification Changes (Mark-up) cc: Mr. Elmo E. Collins, Jr. NRC Senior Resident Inspector Regional Administrator, Region IV Grand Gulf Nuclear Station U. S. Nuclear Regulatory Commission Port Gibson, MS 39150 612 East Lamar Blvd., Suite 400 Arlington, TX 76011-4125 U. S. Nuclear Regulatory Commission State Health Officer ATTN: Mr. A. B. Wang, NRR/DORL (w/2) Mississippi Department of Health ATTN: ADDRESSEE ONLY P. O. Box 1700 ATTN: Courier Delivery Only Jackson, MS 39215-1700 Mail Stop OWFN/8 B1 11555 Rockville Pike Rockville, MD 20852-2378

Attachment 1 GNRO-2012/00024 Grand Gulf Nuclear Station Extended Power Uprate Revised Technical Specification Changes (Mark-up)

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more Functions C.1 Restore RPS trip 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> with RPS trip capability.

capability not maintained.

D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition A, Table 3.3.1.1-1 for B, or C not met. the channel.

E. As required by E.1 Reduce THERMAL POWER 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Required Action D.1 to < 40% RTP.

and referenced in Table 3.3.1.1-1.

35.4%

F. As required by F.1 Reduce THERMAL POWER 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Required Action D.1 to < 25% RTP.

and referenced in Table 3.3.1.1-1.

21.8%

G. As required by G.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Required Action D.1 and referenced in Table 3.3.1.1-1.

H. As required by H.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Required Action D.1 and referenced in Table 3.3.1.1-1.

(continued)

GRAND GULF 3.3-2 Amendment No. 120, 188,

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I. As required by I.1 Initiate action to Immediately Required Action D.1 fully insert all and referenced in insertable control Table 3.3.1.1-1. rods in core cells containing one or more fuel assemblies.

J. As required by J.1 Initiate alternate 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Required Action D.1 method to detect and and referenced in suppress thermal Table 3.3.1.1-1. hydraulic instability oscillations.

AND J. 2 ------------ NOTE ------------

LCO 3.0.4 is not applicable.

Restore required 120 days channels to OPERABLE.

K. Required Action and K.1 Reduce THERMAL POWER 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion to < 24% RTP.

Time of Condition J not met.

21%

GRAND GULF 3.3-2a Amendment No. 188,

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.20 ---------------------------NOTE---------------------------

1. For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.

2. For Functions 2.a, 2.b, and 2.c, the APRM/OPRM channels and the 2-Out-Of-4 Voter channels are included in the CHANNEL FUNCTIONAL TEST.

3. For Functions 2.d and 2.f, the APRM/OPRM channels and the 2-Out-Of-4 Voter channels plus the flow input function, excluding the flow transmitters, are included in the CHANNEL FUNCTIONAL TEST.

Perform CHANNEL FUNCTIONAL TEST. 184 days SR 3.3.1.1.21 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months SR 3.3.1.1.22 --------------------NOTE-----------------------

For Function 2.e, n equals 8 channels for the purpose of determining the STAGGERED TEST BASIS Frequency. Testing APRM and OPRM outputs shall alternate.

Verify the RPS RESPONSE TIME is within 24 months on a limits. STAGGERED TEST BASIS SR 3.3.1.1.23 Verify OPRM is not bypassed when APRM 24 months Simulated Thermal Power is greater than or equal to 29% RTP and recirculation drive flow is less than 60% of rated recirculation drive flow. 26%

GRAND GULF 3.3-5b Amendment No. 188,

RPS Instrumentation 3.3.1.1 4

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 Flux C High 2 3 H SR 3.3.1.1.1 122/125 SR 3.3.1.1.3 divisions SR 3.3.1.1.12 of full SR 3.3.1.1.13 scale 5(a) 3 I SR 3.3.1.1.1 SR 3.3.1.1.4 122/125 SR 3.3.1.1.12 divisions SR 3.3.1.1.13 of full scale

b. Inop 2 3 H SR 3.3.1.1.3 NA SR 3.3.1.1.13 5(a) 3 I SR 3.3.1.1.4 NA SR 3.3.1.1.13

2. Average Power Range Monitors

a. Neutron Flux C High, 2 3(c) H SR 3.3.1.1.7 20% RTP Setdown SR 3.3.1.1.10(d)(e)

SR 3.3.1.1.19 SR 3.3.1.1.20 119.3%

b. Fixed Neutron 1 3(c) G SR 3.3.1.1.2 120% RTP Flux C High SR 3.3.1.1.7 SR 3.3.1.1.10(d)(e)

SR 3.3.1.1.19 SR 3.3.1.1.20

c. Inop 1,2 3(c) H SR 3.3.1.1.20 NA

d. Flow Biased Simulated 1 3(c) G SR 3.3.1.1.2 (b)

Thermal Power - High SR 3.3.1.1.7 SR 3.3.1.1.10(d)(e)

SR 3.3.1.1.17 SR 3.3.1.1.19 SR 3.3.1.1.20

e. 2-Out-Of-4 Voter 1,2 2 H SR 3.3.1.1.19 NA SR 3.3.1.1.20 SR 3.3.1.1.21 21% SR 3.3.1.1.22

f. OPRM Upscale 24% RTP 3(c) J SR 3.3.1.1.7 (f)

SR 3.3.1.1.10(d)(e)

SR 3.3.1.1.19 SR 3.3.1.1.20 SR 3.3.1.1.23 (continued)

GRAND GULF 3.3-6 Amendment No. 141,169,188,

Table 3.3.1.1-1 (page 2 of 4)

RPS Instrumentation Reactor Protection System Instrumentation 3.3.1.1 (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies. 0.58W + 59.1% RTP (b) Two-Loop Operation 0.65W + 62.9% RTP and 113% RTP Single-Loop Operation 0.65W + 42.3% RTP 0.58W + 37.4% RTP (c) Each channel provides inputs to both trip systems.

(d) If the as-found channel setpoint is outside its pre-defined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(e) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures to confirm channel performance. The NTSP and the methodologies used to determine the as-found and as-left tolerances are specified in the Technical Requirements Manual.

(f) The setpoint for the OPRM Upscale Period-Based Detection algorithm is specified in the COLR.

GRAND GULF 3.3-6a Amendment No. 188,

RPS Instrumentation 3 of 4 3.3.1.1 Table 3.3.1.1-1 (page 2 of 3)

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

3. Reactor Vessel Steam Dome 1,2 2 H SR 3.3.1.1.1 1079.7 psig Pressure C High SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.15

4. Reactor Vessel Water 1,2 2 H SR 3.3.1.1.1 10.8 inches Level C Low, Level 3 SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.12 21.8% SR 3.3.1.1.13 SR 3.3.1.1.15

5. Reactor Vessel Water 25% RTP 2 F SR 3.3.1.1.1 54.1 inches Level C High, Level 8 SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.15

6. Main Steam Isolation 1 8 G SR 3.3.1.1.8 7% closed Valve C Closure SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.15

7. Drywell Pressure C High 1,2 2 H SR 3.3.1.1.1 1.43 psig SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.12 SR 3.3.1.1.13

8. Scram Discharge Volume Water Level C High

a. Transmitter/Trip Unit 1,2 2 H SR 3.3.1.1.1 63% of full SR 3.3.1.1.8 scale SR 3.3.1.1.9 SR 3.3.1.1.12 SR 3.3.1.1.13 5(a) 2 I SR 3.3.1.1.1 63% of full SR 3.3.1.1.8 scale SR 3.3.1.1.9 SR 3.3.1.1.12 SR 3.3.1.1.13

b. Float Switch 1,2 2 H SR 3.3.1.1.8 65 inches SR 3.3.1.1.12 SR 3.3.1.1.13 5(a) 2 I SR 3.3.1.1.8 65 inches SR 3.3.1.1.12 SR 3.3.1.1.13 (continued)

(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

GRAND GULF 3.3-7 Amendment No. 120

RPS Instrumentation 3.3.1.1 4 of 4 Table 3.3.1.1-1 (page 3 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

9. Turbine Stop Valve Closure, 40% RTP 4 E SR 3.3.1.1.8 37 psig Trip Oil Pressure C Low SR 3.3.1.1.9 SR 3.3.1.1.12 35.4% SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15

10. Turbine Control Valve 40% RTP 2 E SR 3.3.1.1.8 42 psig Fast Closure, Trip Oil SR 3.3.1.1.9 Pressure C Low SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15

11. Reactor Mode 1,2 2 H SR 3.3.1.1.11 NA Switch C Shutdown Position SR 3.3.1.1.13 5(a) 2 I SR 3.3.1.1.11 NA SR 3.3.1.1.13

12. Manual Scram 1,2 2 H SR 3.3.1.1.4 NA SR 3.3.1.1.13 5(a) 2 I SR 3.3.1.1.4 NA SR 3.3.1.1.13 (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

GRAND GULF 3.3-8 Amendment No. 120