GNRO-2014/00031, Response to Electronic Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 3/18/2014: Difference between revisions

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{{#Wiki_filter: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-2014/00031 April 11 ,2014 u.s.Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
{{#Wiki_filter: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-2014/00031 April 11 ,2014 u.s. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001


==SUBJECT:==
==SUBJECT:==
Response to Electronic Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, dated 3/18/2014 Grand Gulf Nuclear Station, Unit 1 Docket No.50-416 License No.NPF-29  
Response to Electronic Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, dated 3/18/2014 Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29


==REFERENCES:==
==REFERENCES:==
1  Electronic Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request Dated 3/18/2014 (TAC MF2798) 2  Entergy Letter, "Maximum Extended Load Line Limit Analysis Plus (MELLLA+) License Amendment Request," GNRO-2013/00012, dated September 25, 2013 (ADAMS Accession No. ML13269A140).


1 Electronic Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request Dated 3/18/2014 (TAC MF2798)2 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 1 the revised mark-up pages and in Attachment 2, the revised clean technical specification pages requested in the Reference 1 Request for Additional Information (RAI).
This letter contains no new commitments. If you have any questions or require additional information, please contact Mr. Jeffery Seiter at 601-437-2344.
I declare under penalty of perjury that the foregoing is true and correct; executed on April 11, 2014.
Sincerely,
~,f----            ------2--
KJM/jas                                  .:::>
Attachments:    1  Request for Additional Information - Revised Technical Specification Mark-up Pages 2  Request for Additional Information - Revised Technical Specification Clean Pages cc: (see next page)
 
GNRO-2014/00031 Page 2 of 2 cc: with Attachment 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 G14 Washington, DC 20555-0001 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 to GNRO-2014/00031 Request for Additional Information - Revised Technical Specification Mark-up 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 Re 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    etion and K.1  Reduce THERMAL POWER asso ated Completion      to < 21% RTP.
      " e of Condition J not met.
GRAND GULF                    3.3-2a              Amendment No. ~,    ~
 
INSERT TS-l J. As required by        J.1 Initiate action to    Immediately Required Action D.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 hours Automated BSP Scram region using the modified APRM Flow Biased simulated Thermal Power - High rip function setpoints defined in the COLR.
J.3 Initiate action to    Immediately submit an OPRM report in accordance with Specification 5.6.7.
K. Required Action and  K.1 Initiate action to    Immediately associated Com~letion    implement the Manual Time of Conditlon J      BSP Regions defined not met.                  in the COLR.
AND K.2 Reduce operation to  12 hours below 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  L.1 Reduce THERMAL POWER  4 hours associated Completion      to < 16.8% RTP.
Time of Condition J not met.


==Dear Sir or Madam:==
Reporting Requirements 5.6 5.6   Reporting Requirements 5.6.6       Reactor Coolant System (RCS) Pressure and Temperature Limits       Report (PTLR)
Entergy Operations, Inc.is providing in Attachment 1 the revised mark-up pages and in Attachment 2, the revised clean technical specification pages requested in the Reference 1 Request for Additional Information (RAI).This letter contains no new commitments.
: 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:
If you have any questions or require additional information, please contact Mr.Jeffery Seiter at 601-437-2344.
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"
I declare under penalty of perjury that the foregoing is true and correct;executed on April 11, 2014.Sincerely,
: 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:
------2--KJM/jas.:::>Attachments:
i)     NEDC-33178P-A, "GE Hitachi Nuclear Energy Methodology for Development of Reactor Pressure Vessel Temperature Curves" Revision 1, June 2009
1 Request for Additional Information
: c.     The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.
-Revised Technical Specification Mark-up Pages 2 Request for Additional Information
GRAND GULF                             5.0-21a                       Amendment No. +9i
-Revised Technical Specification Clean Pages cc: (see next page)
 
GNRO-2014/00031 Page 2 of 2 cc: with Attachment 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 G 14 Washington, DC 20555-0001 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 to GNRO-2014/00031 Request for Additional Information
Attachment 2 to GNRO-2014/00031 Request for Additional Information - Revised Technical Specification Clean Pages
-Revised Technical Specification Mark-up Pages RPS Instrumentation 3.3.1.1 ACTIONS (continued)
 
CONDITION REQUIRED ACTION COMPLETION TIME I.As required by Required Action 0.1 and referenced in Table 3.3.1.1-1.
RPS Instrumentation 3.3.1.1 ACTIONS   (continued)
1.1 Initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies.
CONDITION           REQUIRED ACTION          COMPLETION TIME I. As required by       1.1  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.
Immediately 120 days Reduce THERMAL POWER to<21%RTP.Initiate alternate method to detect and suppress thermal hydraulic instability oscillations.
J. As required by       J.1  Initiate action to      Immediately Required Action D.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 hours Automated BSP Scram region using the modified APRM Flow Biased simulated Thermal Power - High rip function setpoints defined in the COLR.
AND J.1 K.1 s required by Re ired Action 0.1 and r erenced in Table 3...1-1.K.Require etion and asso ated Completion"e of Condition J not met.GRAND GULF 3.3-2a Amendment No.
J.3  Initiate action to     Immediately submit an OPRM report in accordance with Specification 5.6.7.
INSERT TS-l J.As required by Required Action D.1 and referenced in Table 3.3.1.1-1.
K. Required Action and  K.1  Initiate action to     Immediately associated Completion      implement the Manual Time of Conditlon J        BSP Regions defined not met.                  in the COLR.
K.Required Action and associated Time of Conditlon J not met.L.Required Action and associated Completion Time of Condition J not met.J.1 AND J.2 J.3 K.1 AND K.2 AND K.3 L.1 Initiate action to implement the Manual BSP regions defined in the COLR Implement the Automated BSP Scram region using the modified APRM Flow Biased simulated Thermal Power-High rip function setpoints defined in the COLR.Initiate action to submit an OPRM report in accordance with Specification 5.6.7.Initiate action to implement the Manual BSP Regions defined in the COLR.Reduce operation to below the BSP Boundary defined in the COLR.-------NOTELCO 3.0.4 is not applicable.
AND K.2  Reduce operation to     12 hours below the BSP Boundary defined in the COLR.
Restore required channels to OPERABLE.Reduce THERMAL POWER to<16.8%RTP.Immediately 12 hours Immediately Immediately 12 hours 120 days 4 hours 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:
AND K.3  ------- NOTE --------  120 days LCO 3.0.4 is not applicable.
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.GRAND GULF 5.0-21a Amendment No.+9i Attachment 2 to GNRO-2014/00031 Request for Additional Information
Restore required channels to OPERABLE.
-Revised Technical Specification Clean Pages ACTIONS (continued)
L. Required Action and  L.1  Reduce THERMAL POWER   4 hours associated Completion      to < 16.8% RTP.
CONDITION I.As required by Required Action D.1 and referenced in Table 3.3.1.1-1.
Time of Condition J GRAND GULF                    3.3-2a                   Amendment No. ~
J.As required by Required Action D.1 and referenced in Table 3.3.1.1-1.
 
K.Required Action and associated Completion Time of Conditlon J not met.L.Required Action and associated Completion Time of Condition J GRAND GULF 1.1 J.1 AND J.2 J.3 K.1 AND K.2 AND K.3 L.1 REQUIRED ACTION Initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies.
Reporting Requirements 5.6 5.6   Reporting Requirements 5.6.6       Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
Initiate action to implement the Manual BSP regions defined in the COLR Implement the Automated BSP Scram region using the modified APRM Flow Biased simulated Thermal Power-High rip function setpoints defined in the COLR.Initiate action to submit an OPRM report in accordance with Specification 5.6.7.Initiate action to implement the Manual BSP Regions defined in the COLR.Reduce operation to below the BSP Boundary defined in the COLR.-------NOTELCO 3.0.4 is not applicable.
: 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:
Restore required channels to OPERABLE.Reduce THERMAL POWER to<16.8%RTP.3.3-2a RPS Instrumentation 3.3.1.1 COMPLETION TIME Immediately Immediately 12 hours Immediately Immediately 12 hours 120 days 4 hours Amendment No.
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"
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:
: 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)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.+/-9i}}
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. +/-9i}}

Revision as of 05:49, 4 November 2019

Response to Electronic Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 3/18/2014
ML14104A144
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 04/11/2014
From: Kevin Mulligan
Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2014/00031
Download: ML14104A144 (9)
v • d • e


Text

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-2014/00031 April 11 ,2014 u.s. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Response to Electronic Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, dated 3/18/2014 Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29

REFERENCES:

1 Electronic Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request Dated 3/18/2014 (TAC MF2798) 2 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 1 the revised mark-up pages and in Attachment 2, the revised clean technical specification pages requested in the Reference 1 Request for Additional Information (RAI).

This letter contains no new commitments. If you have any questions or require additional information, please contact Mr. Jeffery Seiter at 601-437-2344.

I declare under penalty of perjury that the foregoing is true and correct; executed on April 11, 2014.

Sincerely,

~,f---- ------2--

KJM/jas .:::>

Attachments: 1 Request for Additional Information - Revised Technical Specification Mark-up Pages 2 Request for Additional Information - Revised Technical Specification Clean Pages cc: (see next page)

GNRO-2014/00031 Page 2 of 2 cc: with Attachment 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 G14 Washington, DC 20555-0001 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 to GNRO-2014/00031 Request for Additional Information - Revised Technical Specification Mark-up 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 Re 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 etion and K.1 Reduce THERMAL POWER asso ated Completion to < 21% RTP.

" e of Condition J not met.

GRAND GULF 3.3-2a Amendment No. ~, ~

INSERT TS-l J. As required by J.1 Initiate action to Immediately Required Action D.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 rip function setpoints defined in the COLR.

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

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

AND K.2 Reduce operation to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> below 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 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 J not met.

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.

GRAND GULF 5.0-21a Amendment No. +9i

Attachment 2 to GNRO-2014/00031 Request for Additional Information - Revised Technical Specification Clean 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 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 action to Immediately Required Action D.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 rip function setpoints defined in the COLR.

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

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

AND K.2 Reduce operation to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> below 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 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 J GRAND GULF 3.3-2a Amendment No. ~

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. +/-9i

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