GNRO-2014/00031, 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  |
| 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) | |
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, 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 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 Required Action 0.1 and referenced in Table 3.3.1.1-1.
1.1 Initiate action to fully insert all insertable control 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.
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.
~,
~
INSERT TS-l J.
As required by Required Action D.1 and referenced in Table 3.3.1.1-1.
K.
Required Action and associated Com~letion 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.
NOTE --------
LCO 3.0.4 is not applicable.
Restore required channels to OPERABLE.
Reduce THERMAL POWER to < 16.8% RTP.
Immediately 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Immediately Immediately 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 120 days 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
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 to GNRO-2014/00031 Request for Additional Information - Revised Technical Specification Clean Pages
ACTIONS (continued)
CONDITION I.
As required by Required Action D.1 and referenced in Table 3.3.1.1-1.
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.
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.
NOTE --------
LCO 3.0.4 is not applicable.
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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Immediately Immediately 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 120 days 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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