GNRO-2015/00080, License Renewal Application 2015 Annual Update
| ML15344A283 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 12/10/2015 |
| From: | Kevin Mulligan Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GNRO-2015/00080 | |
| Download: ML15344A283 (9) | |
Text
'!:::O'Entergy GNRO-2015/00080 December 10, 2015 u.s. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Entergy Operations, Inc.
P. O. Box 756 Port Gibson, MS 39150 Kevin Mulligan Vice President, Operations Grand Gulf Nudear Station Tel. (601) 437-7500
SUBJECT:
REFERENCES:
Dear Sir or Madam:
License Renewal Application 2015 Annual Update Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29 1.
Letter to Nuclear Regulatory Commission, "License Renewal Application Grand Gulf Nuclear Station, Unit 1," dated October 28, 2011 (GNRO-2011/00093) 2.
License Renewal Annual Update 2015, Engineering Report No.
GGNS-RPT-EP-15-00001, Revision 0, dated November 19,2015 The purpose of this letter is to provide the Nuclear Regulatory Commission (NRC) an annual update to the referenced Grand Gulf Nuclear Station (GGNS) License Renewal Application (LRA), in accordance with 10 CFR 54.21 (b). During NRC review of the GGNS LRA, GGNS is required by 10 CFR 54.21(b) to provide an annual report of changes to the GGNS current licensing basis (CLB) that materially affects the contents of the GGNS LRA, including the Final Safety Analysis Report supplement. GGNS has completed the annual CLB review and is providing, in the Attachment, the changes to the LRA required by this review.
This letter contains no new commitments.
If you have any questions or require additional information, please contact James Nadeau at 601-437-2103.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on the 10th day of December, 2015.
KJM/ras
GNRO-2015/00080 Page 2 of 2
Attachment:
Current License Basis Changes to the License Renewal Application cc: with Attachment U.S. Nuclear Regulatory Commission ATTN: Ms. Rebecca Richardson, NRRlDLR Project Manager Office of License Renewal Mail Stop 0-11 F1 Washington, DC 20555 cc: without Attachment U.S. Nuclear Regulatory Commission ATTN: Mr. Mark Dapas Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 1600 East Lamar Boulevard Arlington, TX 76011-4511 U.S. Nuclear Regulatory Commission ATTN: Mr. A. Wang, NRRlDORL Mail Stop OWFN/8 G14 11555 Rockville Pike Rockville, MD 20852-2378 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150
Attachment to GNRO-2015/00080 Current License Basis Changes to the License Renewal Application
Attachment to GNRO-2015/00080 Page 1 of 6 Grand Gulf Nuclear Station, Unit 1 (GGNS) current licensing basis (CLB) documents have been reviewed and any changes that have a material effect on the License Renewal Application (LRA) have been identified.
Methodology The following documents were reviewed:
Design Changes and Evaluations: Engineering Changes (ECs)
LRA Piping and Instrumentation Diagrams Updated Final Safety Analysis Report (UFSAR) and Safe Shutdown Analysis NRC Correspondence (ADAMS Search and GGNS NRC Correspondence)
This review includes documents affecting the CLB that became effective during the period of May31, 2014 through May31, 2015.
The emphasis of these reviews is to identify changes that materially affect the LRA.
CLB documents requiring a change to the LRA are identified in the following table along with the LRA section affected:
Affected LRA Sections CLB Change LRA Section Affected GNR12014-00080 ISSUANCE OF AMENDMENT 198 TO THE GGNS TECH SPECS SECTION 1.2 INCREASED THERMAL POWER LEVEL FOR EPU EC-25799 RHR B SIGHT GLASS TABLE 2.3.2-8-1 INSTALLATION FOR VENTING TABLE 3.2.2-8-1 ADDED: SIGHT GLASS AS COMPONENT TYPE EC-54570 EVALUATION FOR 1P81C002 HPCS DIESEL DRIVEN AIR COMPRESSOR TABLE 2.3.3-19-28 REPLACEMENT TABLE 3.3.2-19-28 ADDED: COMPRESSOR HOUSING OF CAST IRON AS COMPONENT TYPE/MATERIAL
Attachment to GNRO-2015/00080 Page 2 of 6 CLB Change LRA Section Affected EC-26034 PROVIDE ALTERNATE ROUTING OF NOBLE CHEM MITIGATION TABLE 2.3.3-19-29 MONITOR TO CHEMICAL WASTE TABLE 3.3.2-19-29 SUMP ADDED: STAINLESS STEEL PIPING MATERIAL ADD FUNCTION (3) RELATED TO SECTION 2.3.3.19 -
SAFE SHUTDOWN OF THE MISCELLANEOUS AUXILIARY SUPPRESSION POOL CLEAN UP SYSTEMS IN SCOPE FOR 10 SYSTEM.
CFR 54.4(A)(2) - SPCU
Attachment to GNRO-2015/00080 Page 3 of6 Affected LRA sections and specific changes to the LRA are shown below:
Changes are shown as strikethroughs for deletions and underlines for additions.
1.2 PLANT DESCRIPTION The GGNS site is located in Claiborne County, Mississippi, on the east bank of the Mississippi River, approximately 25 miles south-southwest of Vicksburg, Mississippi, and 37 miles north northeast of Natchez, Mississippi. The site is bounded by the Mississippi River on the west and by land owned by others on the north, south, and east.
GGNS uses a single cycle, forced circulation, boiling water reactor (GE BWR-6). General Electric Company (GE) furnished the nuclear steam supply system (NSSS) and Allis-Chalmers Power Systems furnished the turbine generator set. The Grand Gulf containment is a Mark III BWR containment incorporating the dryweillpressure suppression concept. The containment is a steel-lined reinforced concrete structure designed by Bechtel Power Corporation. The NSSS is licensed to generate 3898 megawatts-thermal (MWt).
Amendment 198 to the GGNS Operating License was issued by the NRC in 2014 to increase the thermal power level to 4408 MWt for the Upon approval for an extended power uprate (EPU). scheduled to occur jn 2012, the licensed thermal power level will be 4408 MWt. The planned EPU is a constant pressure power upratethat maintains the same maximum operating primary system pressure. Changes to operating_parameters due to the increase in power were considered during preparation of the license_renewal application.
Section 2.3.3.19 Suppression Pool Cleanup (SPCU)
The SPCU system has the following intended function for 10 CFR 54.4(a)(3):
Perform a function (isolate suppression pool flow to the precoat filters) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48),
Attachment to GNRO-2015/00080 Page 4 of 6 Table 2.3.2-8-1 Residual Heat Removal System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Sight glass Pressure boundary Table 3.2.2-8-1 Residual Heat Removal System Nonsafety-Related Components Affecting Safety-Related Systems S
fA*
M tE I
f ummary 0
~glng anagemen va ua Ion Table 3.2.2-8-1: Residual Heat Removal System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Table Component Intended Requiring Management NUREG-1 Type Function Material Environment Management Program 1801 Item Item Notes Sight Pressure Glass Air-indoor None None V.F.EP-16 3.2.1-8 glass boundary (ext) 60 Sight Pressure Glass Treated None None V.F.EP-29 3.2.1-8 glass boundary water (int) 60 Sight Pressure Copper Air - indoor None None V.F.EP-10 3.2.1-8 glass boundary alloy>
(ext) 57 15%
Zn or>
8% AI Sight Pressure Copper Treated Loss of Selective VII.E3.AP-3.3.1-Q glass boundary alloy>
water (int) material Leaching 32 72 15%
Zn or>
_u%AI
~_.
Sight Pressure Copper Treated Loss of Water VII.E3.AP-3.3.1-c, glass boundary alloy>
water (int) material Chemistry 140 22 201 15%
Control-Zn or >
BWR 8% AI
Attachment to GNRO-2015/00080 Page 50f6 Table 2.3.3-19-28 HPCS Diesel Generator System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function1 Compressor housing Pressure boundary Table 3.3.2-19-28 HPCS Diesel Generator System Nonsafety-Related Components Affecting Safety-Related Systems' S
fA*
M tE I
f ummaryo
~glng anagemen va ua Ion Table 3.3.2-19-28:
HPCS Diesel Generator System [10 CFR 54.4(a)(2)]
Aging Effect Aging NUREG-Table Component Intended Requiring Management 1801 1
Type Function Material Environment Management Program Item' Item Notes Compressor Pressure Cast Air - indoor Loss of External VII.I.A-77 3.3.1-A housing boundary iron (ext) material Surfaces 78 Monitoring Compressor Pressure Cast Condensation Loss of Internal VII.F1.A-3.3.1-C housing boundary iron (int) material Surfaces in 08 90 Miscellaneous Piping and Ducting Components
Attachment to GNRO-2015/00080 Page 6 of6 Table 2.3.3-19-29 NobleChem' Injection and Monitoring System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Intended Function1 Pressure boundar Table 3.3.2-19-29 NobleChem Injection and Monitoring System Nonsafety-Related Components Affecting Safety-Related Systems S
fA*
M tE I
f ummary 0
~glng anagemen va ua Ion Table 3.3.2-19-29:
NobleChem Injection and Monitoring System [10 CFR 54.4(a)(2)]
Aging Effect Aging Table Component Intended Requiring Management NUREG-1 Type.
Function Material Environment Management.
Program 1801 Item Item Notes Piping Pressure Stainless Indoor air None None VII.J.AP-3.3.1-
~
boundary steel (ext) 123 120 Piping Pressure Stainless Treated Loss of Water VII.E3.AP-3.3.1-C*
.:...I.
boundary steel water (int) material Chemistry 110 25 301 Control-BWR EiQlng Pressure Stainless Treated Cracking Water VIII.E.SP-3.4.1-c, boundary steel water Chemistry 88 11 301
> 140°F Control-(int)
'!:::O'Entergy GNRO-2015/00080 December 10, 2015 u.s. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Entergy Operations, Inc.
P. O. Box 756 Port Gibson, MS 39150 Kevin Mulligan Vice President, Operations Grand Gulf Nudear Station Tel. (601) 437-7500
SUBJECT:
REFERENCES:
Dear Sir or Madam:
License Renewal Application 2015 Annual Update Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29 1.
Letter to Nuclear Regulatory Commission, "License Renewal Application Grand Gulf Nuclear Station, Unit 1," dated October 28, 2011 (GNRO-2011/00093) 2.
License Renewal Annual Update 2015, Engineering Report No.
GGNS-RPT-EP-15-00001, Revision 0, dated November 19,2015 The purpose of this letter is to provide the Nuclear Regulatory Commission (NRC) an annual update to the referenced Grand Gulf Nuclear Station (GGNS) License Renewal Application (LRA), in accordance with 10 CFR 54.21 (b). During NRC review of the GGNS LRA, GGNS is required by 10 CFR 54.21(b) to provide an annual report of changes to the GGNS current licensing basis (CLB) that materially affects the contents of the GGNS LRA, including the Final Safety Analysis Report supplement. GGNS has completed the annual CLB review and is providing, in the Attachment, the changes to the LRA required by this review.
This letter contains no new commitments.
If you have any questions or require additional information, please contact James Nadeau at 601-437-2103.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on the 10th day of December, 2015.
KJM/ras
GNRO-2015/00080 Page 2 of 2
Attachment:
Current License Basis Changes to the License Renewal Application cc: with Attachment U.S. Nuclear Regulatory Commission ATTN: Ms. Rebecca Richardson, NRRlDLR Project Manager Office of License Renewal Mail Stop 0-11 F1 Washington, DC 20555 cc: without Attachment U.S. Nuclear Regulatory Commission ATTN: Mr. Mark Dapas Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 1600 East Lamar Boulevard Arlington, TX 76011-4511 U.S. Nuclear Regulatory Commission ATTN: Mr. A. Wang, NRRlDORL Mail Stop OWFN/8 G14 11555 Rockville Pike Rockville, MD 20852-2378 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150
Attachment to GNRO-2015/00080 Current License Basis Changes to the License Renewal Application
Attachment to GNRO-2015/00080 Page 1 of 6 Grand Gulf Nuclear Station, Unit 1 (GGNS) current licensing basis (CLB) documents have been reviewed and any changes that have a material effect on the License Renewal Application (LRA) have been identified.
Methodology The following documents were reviewed:
Design Changes and Evaluations: Engineering Changes (ECs)
LRA Piping and Instrumentation Diagrams Updated Final Safety Analysis Report (UFSAR) and Safe Shutdown Analysis NRC Correspondence (ADAMS Search and GGNS NRC Correspondence)
This review includes documents affecting the CLB that became effective during the period of May31, 2014 through May31, 2015.
The emphasis of these reviews is to identify changes that materially affect the LRA.
CLB documents requiring a change to the LRA are identified in the following table along with the LRA section affected:
Affected LRA Sections CLB Change LRA Section Affected GNR12014-00080 ISSUANCE OF AMENDMENT 198 TO THE GGNS TECH SPECS SECTION 1.2 INCREASED THERMAL POWER LEVEL FOR EPU EC-25799 RHR B SIGHT GLASS TABLE 2.3.2-8-1 INSTALLATION FOR VENTING TABLE 3.2.2-8-1 ADDED: SIGHT GLASS AS COMPONENT TYPE EC-54570 EVALUATION FOR 1P81C002 HPCS DIESEL DRIVEN AIR COMPRESSOR TABLE 2.3.3-19-28 REPLACEMENT TABLE 3.3.2-19-28 ADDED: COMPRESSOR HOUSING OF CAST IRON AS COMPONENT TYPE/MATERIAL
Attachment to GNRO-2015/00080 Page 2 of 6 CLB Change LRA Section Affected EC-26034 PROVIDE ALTERNATE ROUTING OF NOBLE CHEM MITIGATION TABLE 2.3.3-19-29 MONITOR TO CHEMICAL WASTE TABLE 3.3.2-19-29 SUMP ADDED: STAINLESS STEEL PIPING MATERIAL ADD FUNCTION (3) RELATED TO SECTION 2.3.3.19 -
SAFE SHUTDOWN OF THE MISCELLANEOUS AUXILIARY SUPPRESSION POOL CLEAN UP SYSTEMS IN SCOPE FOR 10 SYSTEM.
CFR 54.4(A)(2) - SPCU
Attachment to GNRO-2015/00080 Page 3 of6 Affected LRA sections and specific changes to the LRA are shown below:
Changes are shown as strikethroughs for deletions and underlines for additions.
1.2 PLANT DESCRIPTION The GGNS site is located in Claiborne County, Mississippi, on the east bank of the Mississippi River, approximately 25 miles south-southwest of Vicksburg, Mississippi, and 37 miles north northeast of Natchez, Mississippi. The site is bounded by the Mississippi River on the west and by land owned by others on the north, south, and east.
GGNS uses a single cycle, forced circulation, boiling water reactor (GE BWR-6). General Electric Company (GE) furnished the nuclear steam supply system (NSSS) and Allis-Chalmers Power Systems furnished the turbine generator set. The Grand Gulf containment is a Mark III BWR containment incorporating the dryweillpressure suppression concept. The containment is a steel-lined reinforced concrete structure designed by Bechtel Power Corporation. The NSSS is licensed to generate 3898 megawatts-thermal (MWt).
Amendment 198 to the GGNS Operating License was issued by the NRC in 2014 to increase the thermal power level to 4408 MWt for the Upon approval for an extended power uprate (EPU). scheduled to occur jn 2012, the licensed thermal power level will be 4408 MWt. The planned EPU is a constant pressure power upratethat maintains the same maximum operating primary system pressure. Changes to operating_parameters due to the increase in power were considered during preparation of the license_renewal application.
Section 2.3.3.19 Suppression Pool Cleanup (SPCU)
The SPCU system has the following intended function for 10 CFR 54.4(a)(3):
Perform a function (isolate suppression pool flow to the precoat filters) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48),
Attachment to GNRO-2015/00080 Page 4 of 6 Table 2.3.2-8-1 Residual Heat Removal System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function Sight glass Pressure boundary Table 3.2.2-8-1 Residual Heat Removal System Nonsafety-Related Components Affecting Safety-Related Systems S
fA*
M tE I
f ummary 0
~glng anagemen va ua Ion Table 3.2.2-8-1: Residual Heat Removal System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Table Component Intended Requiring Management NUREG-1 Type Function Material Environment Management Program 1801 Item Item Notes Sight Pressure Glass Air-indoor None None V.F.EP-16 3.2.1-8 glass boundary (ext) 60 Sight Pressure Glass Treated None None V.F.EP-29 3.2.1-8 glass boundary water (int) 60 Sight Pressure Copper Air - indoor None None V.F.EP-10 3.2.1-8 glass boundary alloy>
(ext) 57 15%
Zn or>
8% AI Sight Pressure Copper Treated Loss of Selective VII.E3.AP-3.3.1-Q glass boundary alloy>
water (int) material Leaching 32 72 15%
Zn or>
_u%AI
~_.
Sight Pressure Copper Treated Loss of Water VII.E3.AP-3.3.1-c, glass boundary alloy>
water (int) material Chemistry 140 22 201 15%
Control-Zn or >
BWR 8% AI
Attachment to GNRO-2015/00080 Page 50f6 Table 2.3.3-19-28 HPCS Diesel Generator System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Type Intended Function1 Compressor housing Pressure boundary Table 3.3.2-19-28 HPCS Diesel Generator System Nonsafety-Related Components Affecting Safety-Related Systems' S
fA*
M tE I
f ummaryo
~glng anagemen va ua Ion Table 3.3.2-19-28:
HPCS Diesel Generator System [10 CFR 54.4(a)(2)]
Aging Effect Aging NUREG-Table Component Intended Requiring Management 1801 1
Type Function Material Environment Management Program Item' Item Notes Compressor Pressure Cast Air - indoor Loss of External VII.I.A-77 3.3.1-A housing boundary iron (ext) material Surfaces 78 Monitoring Compressor Pressure Cast Condensation Loss of Internal VII.F1.A-3.3.1-C housing boundary iron (int) material Surfaces in 08 90 Miscellaneous Piping and Ducting Components
Attachment to GNRO-2015/00080 Page 6 of6 Table 2.3.3-19-29 NobleChem' Injection and Monitoring System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Intended Function1 Pressure boundar Table 3.3.2-19-29 NobleChem Injection and Monitoring System Nonsafety-Related Components Affecting Safety-Related Systems S
fA*
M tE I
f ummary 0
~glng anagemen va ua Ion Table 3.3.2-19-29:
NobleChem Injection and Monitoring System [10 CFR 54.4(a)(2)]
Aging Effect Aging Table Component Intended Requiring Management NUREG-1 Type.
Function Material Environment Management.
Program 1801 Item Item Notes Piping Pressure Stainless Indoor air None None VII.J.AP-3.3.1-
~
boundary steel (ext) 123 120 Piping Pressure Stainless Treated Loss of Water VII.E3.AP-3.3.1-C*
.:...I.
boundary steel water (int) material Chemistry 110 25 301 Control-BWR EiQlng Pressure Stainless Treated Cracking Water VIII.E.SP-3.4.1-c, boundary steel water Chemistry 88 11 301
> 140°F Control-(int)