GNRO-2015/00059, Submits Corrected Technical Specification Pages Regarding Maximum Extended Load Line Limit Plus License Amendment Request, Dated 9/25/2013

Submits Corrected Technical Specification Pages Regarding Maximum Extended Load Line Limit Plus License Amendment Request, Dated 9/25/2013

ML15226A074
Person / Time
Site:	Grand Gulf
Issue date:	08/14/2015
From:	Kevin Mulligan Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2015/00059
Download: ML15226A074 (21)

Text

~--I

~Entergy Entergy Operations, Inc.

P. O. Box 756 Port Gibson, MS 39150 Kevin Mulligan Site Vice President Grand Gulf Nuclear Station Tel. (601) 437-7400 GNRO-2015/00059 August 13, 2015 u.s. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Corrected Technical Specification Pages Regarding "Maximum Extended Load Line Limit Plus" License Amendment Request, dated 9/25/2013.

Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29

REFERENCES:

1 Entergy Letter, "Maximum Extended Load Line Limit Analysis Plus (MELLLA+) License Amendment Request," GNRO-2013/00012, dated September 25, 2013 (ADAMS Accession No. ML13269A140).

Dear Sir or Madam:

Entergy Operations, Inc. is providing in Attachment 2 clean pages of selected Technical Specification (TS) marked-up pages previously submitted in reference 1. Attachment 1 contains the associated marked-up TS pages for comparison with the clean pages.

The proposed changes to the Grand Gulf Nuclear Station Technical Specifications are attached to this letter. TS page 3.3-2a adds revision bars for J, K and L. TS page 3.3-5b adds the word "deleted" to the blank box at the bottom. TS page 3.3-6 adds revision bars to 2d and 2f. TS page 3.3-6a adds colons and converts double revision bars to single revision bars. TS page 3.4-1 removes a revision bar. TS page 5.0-16 converts double revision bars to single revision bars. TS page 5.0-18 converts a double revision bar to a single revision bar. TS page 5.0-21a removes an indented title for 5.6.7 and adds revision bars.

This letter contains no new commitments.

If you have any questions or require additional information, please contact Mr. James Nadeau at 601-437-2103.

I declare under penalty of perjury that the foregoing is true and correct; executed on August 13, 2015.

GNRO-2015-00059 Page 2 of 2 Sincerely, KJM/ras Attachments: 1. Marked-Up Technical Specification Pages

2. Clean Technical Specification Pages cc: with Attachments U.S. Nuclear Regulatory Commission ATTN: Mr. Marc L. Dapas Regional Administrator, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 U.S. Nuclear Regulatory Commission ATTN: Mr. A. Wang, NRR/DORL Mail Stop OWFN/8 B1 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 State Health Officer Mississippi Department of Health P. O. Box 1700 Jackson, MS 39215-1700

Attachment 1 Grand Gulf Nuclear Station GNRO-2015/00059 Marked-Up Technical Specification Pages

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I. As required by 1.1 Initiate action to Immediately Required Action 0.1 fully insert all and referenced in insertable control Table 3.3.1.1-1. rods in core cells containing one or more fuel assemblies.

s required by J.1 Initiate alternate R ired Action 0.1 method to detect and and r erenced in suppress thermal Table 3 . . . 1-1. hydraulic instability oscillations.

AND 120 days K. Require ction and K.1 Reduce THERMAL POWER ass ated Completion to < 21% RTP.

" e of Condition J not met.

GRAND GULF 3.3-2a Amendment No. ~, +/--9-+/-

INSERT TS-1 J. As required by Required Action J.1 Initiate action to implement Immediately D.1 and referenced in the Manual BSP Regions Table 3.3.1.1-1. defined in the COLR.

AND J.2 Implement the Automated 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> BSP Scram Region using the modified APRM Flow Biased Simulated Thermal Power -

High trip function setpoints defined in the COLR.

AND J.3 Initiate action to submit an 90 days OPRM report in accordance with Specification 5.6.7.

K. Required Action and associated K.1 Initiate action toimplement Immediately Completion Time of Condition J the Manual BSP Regions not met. defined in the COLR.

AND K.2 Reduce operation to below 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> the BSP Boundary defined in the COLR.

AND K.3 - - - - - - - - NOTE - - - - - - - - 120 days LCO 3.0.4 is not applicable.

Restore required channels to OPERABLE.

L. Required Action and associated L.1 Reduce THERMAL POWER 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time ofCondition K to < 16.8% RTP.

not met.

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 2-0ut-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 2-0ut-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 OR J.3d.loll3 OimMlatea 'PheoEmal P6~.eoE is ~EeateE tH8:l'I or eqIJ?l to 26% PTP 2nd ree;rc!lJation Q!iiue fJg\, is less tb.ElP 60g.. of liited FEJeiF81:ila-e.iQR Eh;;i"uQ  ;£"1g" GRAND GULF 3.3-Sb Amendment No.+/-&&r ~

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

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECInED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION 0.1 REQUIREMENTS VALUE

1. Intermediate Range Monitors

a. Neutron Flux - High 2 3 H SR 3.3.1.1.1 s 122/125 SR 3.3.1.1.3 divisions of SR 3.3.1.1.12 full scale SR 3.3.1.1.13 3 SR 3.3.1.1.1 SR 3.3.1.1.4 SR 3.3.1.1.12  ::; 122/125 SR 3.3.1.1.13 divisions of full scale

b. Inop 2 H SR 3.3.1.1.3 NA SR 3.3.1.1.13 3 SR 3. 3. 1. 1. 4 NA SR 3.3.1.1.13

2. Average Power Range Monitors

a. Neutron Flux - 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

b. Fixed Neutron 3 (c) G SR 3.3.1.1.2 S 119.3% RTP Flux - 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 (e) H SR 3.3.1.1.20 NA*~

d. Flow Biased Simulated 3 (c) G SR 3. 3.1. 1. 2 (b)JL:>:.J 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. 2-0ut-Of-4 Voter 1,2 2 H SR 3.3.1.1.19 SR 3.3.1.1.20 SR 3. 3. 1. 1. 21 NA SR 3.3.1.1.22

f. OPRM Upsca Le J SR 3.3.1.1.7 SR 3.3.1.1.10(d) (e)

SR 3.3.1.1.19 (f)

SR 3.3.1.1.20 sa ? :a 1 1 dEl (continued)

GRAND GULF 3.3-6 Amendment No. ~, ~ ~

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

Reactor P ' trumentation (a) With any control rod withd containing one or more fuel assemblies.

(b) Two-Loop Operation 8.58tJ I 59.FJ RTP and 5: 113% RTP Single-Loop Operation O.S8W + 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 provi tolerances apply to the actual setpoint implem to confirm channel performance. The NTSP and the as-found and as-left tolerances are spec'fie Manual.

(f) The setpoint for the OPRM Upscale is specified in the COLR.

OPRM Upscale trip function (Function 2.f) inoperable, reset the APRM Flow Biased Simulated Thermal Power - High trip function (Function 2.d) setpoints to the values defined by the COLR to implement the Automated BSP Scram Region in accordance with Action J of this specification . ,~

GRAND GULF 3.3-6a Amendment No. ~ ~

Recirculation Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched flows shall be in operation.

ORQ r~H:; rSbil at; en leef) 5Rall be i II OrH~i at; on wi-ttl ttre rEH~6lired limits meelified fer :511'19le 1001' 0l'eiation as

~pQbifiQd iR tR8 COL~.

- - - - - - - - - - - - - - - - - - - - - - - - - - -NOT E- - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Required limit modifications for single recirculation loop operation may be delayed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after transition from two recirculation loop operation to single recirculation loop operation.

APPLICABI ITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reci culation loop jet A.I Shutdown one 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> pump flow mismatch not recirculation loop.

wi th n 1i mi ts .

141 GRAND GULF 3.4-1 Amendment No. ~,

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.11 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

1. A change in the TS incorporated in the license; or

2. A change to the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.

d. Proposed changes that do not meet the criteria of either Specification 5.5.11.b.1 or Specification 5.5.1l.b.2 above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

5.5.12 10 CFR 50, Appendix J, Testing Program This program establishes the leakage rate testing program of the containment as required by 10 CFR 50.54(0) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be implemented in accordance with the Safety Evaluation issued by the Office of Nuclear Reactor Regulation dated April 26, 1995 (GNRI-95/00087) as modified by the Safety Evaluation issued for Amendment No. 135 to the Operating License, except that the next Type A test performed after the November 24, 1993 Type A test shall be performed no later than November 23, 2008. Consistent with standard scheduling practices for Technical Specifications required surveillances, intervals for the recommended surveillance frequency for Type A, Band C testing may be extended by up to 25 percent of the test interval, not to exceed 15 months. The calculated peak containment internal pressure for the design basis loss of coolant accident, Pa, is

~ psig.

GRAND GULF 5.0-16 Amendment No. -l-S+, +64; I-9.J.

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.2 Annual Radiological Environmental Operating Report (continued) results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

5.6.3 Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year shall be submitted by May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the aDCM and process control program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.I.

5.6.4 Deleted 5.6.5 Core Operating Limits Report (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1) LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR) ,

2) LCO 3.2.2, Minimum Critical Power Ratio (MCPR),

3) LCO 3.2.3, Linear Heat Generation Rate (LHGR),

4) ~e1eted

5) LCO 3.3.1.1, RPS Instrumentation, Table 3.3.1.1-1 APRM Function 2.f

6) eeleteel:

The Manual Backup Stability Protection (BSP) Scram Region (Region I), the Manual SSP Controlled Entry Region (Region II), the modified APRM Flow Biased Simulated Thermal Power - High trip function (Function 2.d) setpoints used in the OPRM Automated SSP Scram Region, and the BSP Boundary for Specification 3.3.1.1.

GRAND GULF 5.0-18 Amendment No. -+/--5-=7-, ~ ;.&8

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.6 Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)

a. RCS pressure and temperature limits for heatup, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

i) Limiting Conditions for Operations Section 3.4.11, "RCS Pressure and Temperature (PIT) Limits" ii) Surveillance Requirements Section 3.4.11, "RCS Pressure and Temperature (PIT) Limits"

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) NEDC-33178P-A, "GE Hitachi Nuclear Energy Methodology for Development of Reactor Pressure Vessel Temperature Curves" Revision 1, June 2009

c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.

5.6.7 Oscillation Power Range Monitor (OPRM) Report When an OPRM report is required by CONDITION J of LCO 3.3.1.1, "RPS Instrumentation," it shall be submitted within 90 days of entering CONDITION J. The report shall outline the pre-planned means to provide backup stability protection, the cause of the inoperability, and the plans and schedule for restoring the required instrumentation channels to OPERABLE status.

GRAND GULF 5.0-21a Amendment No. I-9-l

Attachment 2 Grand Gulf Nuclear Station GNRO-2015/00059 Clean Technical Specification Pages

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I. As required by 1.1 Initiate action to Immedlately Required Action 0.1 fully insert all and referenced in insert able control Table 3.3.1.1-1. rods in core cells containing one or more fuel assemblies.

J. As required by J.1 Initiate action to Immediately Required Action 0.1 implement the Manual and referenced in BSP Regions defined Table 3.3.1.1-1. in the COLR.

AND J.2 Implement the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Automated BSP Scram Region using the modified APRM Flow Biased Simulated Thermal Power - High trip function setpoints defined in the COLR.

AND J.3 Initiate action to submit an OPRM report Immediately in accordance with Specification 5.6.7.

K. Required Action and K.1 Initiate action to Immediately associated Completion implement the Manual Time of Condition J BSP Regions defined not met. in the COLR.

AND 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> K.2 Reduce operation to below the BSP Boundary defined in the COLR.

AND

- - 120 days K.3 ------- NOTE - - - - - - - -

LCO 3.0.4 is not applicable.

Restore required channels to OPERABLE.

L. Required Action and L.1 Reduce THERMAL POWER 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion to < 16.8% RTP.

Time of Condition K not met.

GRAND GULF 3.3-2a Amendment No. -+/--8-&,-l-9-+/--,

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 2-0ut-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 2-0ut-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 DELETED DELETED GRAND GULF 3.3-5b Amendment No .-+/--&B-, +/--9-+/-,

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

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

1. Intermediate Range Monitors

a. Neutron Flux - High 2 3 H SR 3.3.1.1.1 ~ 122/125 SR 3.3.1.1.3 divisions of SR 3.3.1.1.12 full scale SR 3.3.1.1.13 5(al 3 I SR 3.3.1.1.1 SR 3.3.1.1.4 ~ 122/125 SR 3.3.1.1.12 divisions of SR 3.3.1.1.13 full scale

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

2. Average Power Range Monitors

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

SR 3.3.1.1.19 SR 3.3.1.1.20

b. Fixed Neutron 1 3(cl G SR 3.3.1.1.2 s 119.3% RTP Flux - High SR 3.3.1.1.7 SR 3.3.1.1.10(dl (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 (bl (gl Thermal Power - High SR 3.3.1.1.7 SR 3.3.1.1.10(dl (e )

SR 3.3.1.1.17 SR 3.3.1.1.19 SR 3.3.1.1.20

e. 2-0ut-Of-4 Voter 1,2 2 H SR 3.3.1.1.19 SR 3.3.1.1.20 SR 3.3.1.1.21 NA SR 3.3.1.1. 22

f. OPRM Upscale ~ 16.8% 3(cl J SR 3.3.1.1.7 RTP SR 3.3.1.1.10(dl (el SR 3.3.1.1.19 (f )

SR 3.3.1.1.20 (continued)

GRAND GULF 3.3-6 Arne ndme n t No. -+/--6-9-, -+/--&8, +/--9-+/-,

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

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

(b) Two-Loop Operation: O.64W + 61.8% RTP and ~ 113% RTP Single-Loop Operation: O.S8W + 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 Confirmation Density Algorithm (CDA) is specified in the COLR.

(g) With the OPRM Upscale trip function (Function 2.f) inoperable, reset the APRM Flow Biased Simulated Thermal Power - High trip function (Function 2.d)setpoints to the values defined by the COLR to implement the Automated BSP Scram Region in accordance with Action J of this specification.

GRAND GULF 3.3-6a Amendment No. -+/--8-8-r +/--9+/-,

Recirculation Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched flows shall be in operation.

OR One recirculation loop shall be in operation provided the plant is not operating in the MELLLA+ domain defined in the COLR and provided the required limits are modified for single loop operation as specified in the COLR.

---

NOTE--------------------------

Required limit modifications for single recirculation loop operation may be delayed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after transition from two recirculation loop operation to single recirculation loop operation.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Recirculation loop A.l Shutdown one 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> jet pump flow Recirculation mismatch not loop within limits (continued)

Grand Gulf 3.4-1 Amendment No. ~, t4l, __

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.11 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

1. A change in the TS incorporated in the license; or

2. A change to the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.

d. Proposed changes that do not meet the criteria of either Specification 5.5.11.b.1 or Specification 5.5.11.b.2 above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

5.5.12 10 CFR 50, Appendix J, Testing Program This program establishes the leakage rate testing program of the containment as required by 10 CFR 50.54(0) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be implemented in accordance with the Safety Evaluation issued by the Office of Nuclear Reactor Regulation dated April 26, 1995 (GNRI-95/00087) as modified by the Safety

~valuation issued for Amendment No. 135 to the Operating License, except that the next Type A test performed after the November 24, 1993 Type A test shall be performed no later than November 23, 2008. Consistent with standard scheduling practices for Technical Specifications required surveillances, intervals for the recommended surveillance frequency for Type A, Band C testing may be extended by up to 25 percent of the test interval, not to exceed 15 months. The calculated peak containment internal pressure for the design basis loss of coolant accident, Pa, is 12.1 psig.

GRAND GULF 5.0-16 Amendment No. $+, -l-64; +9+, _

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.2 Annual Radiological Environmental Operating Report (continued) results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

5.6.3 Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year shall be submitted by May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and process control program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.

5.6.4 Deleted 5.6.5 Core Operating Limits Report (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1) LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR) ,

2) LCO 3.2.2, Minimum Critical Power Ratio (MCPR),

3) LCO 3.2.3, Linear Heat Generation Rate (LHGR),

4) Deleted

5) LCO 3.3.1.1, RPS Instrumentation, Table 3.3.1.1-1 APRM Function 2.f

6) The Manual Backup Stability Protection (BSP) Scram Region (Region 1), the Manual BSP Controlled Entry Region (Region II), the modified APRM Flow Biased Simulated Thermal Power - High trip function (Function 2.d) setpoints used in the OPRM Automated BSP Scram Region, and the BSP Boundary for Specification 3.3.1.1.

(continued)

GRAND GULF 5.0-18 Amendment No. M+, +&+,+88, _ _

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.6 Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)

a. RCS pressure and temperature limits for heatup, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

i) Limiting Conditions for Operations Section 3.4.11, "RCS Pressure and Temperature (PIT) Limits" ii) Surveillance Requirements Section 3.4.11, "RCS Pressure and Temperature (PIT) Limits"

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) NEDC-33178P-A, "GE Hitachi Nuclear Energy Methodology for Development of Reactor Pressure Vessel Temperature Curves" Revision 1, June 2009

c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.

5.6.7 Oscillation Power Range Monitor (OPRM) Report When an OPRM report is required by CONDITION J of LCO 3.3.1.1, "RPS Instrumentation," it shall be submitted within the following 90 days. The report shall outline the preplanned means to provide backup stability protection, the cause of the inoperability, and the plans and schedule for restoring the required instrumentation channels to OPERABLE status.

GRAND GULF 5.0-21a Amendment No. -l-9-l-,