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| issue date = 05/26/2016
| issue date = 05/26/2016
| title = Correction to Amendment No. 207, Request for Changing Five Technical Specifications Allowable Levels
| title = Correction to Amendment No. 207, Request for Changing Five Technical Specifications Allowable Levels
| author name = Kim J S
| author name = Kim J
| author affiliation = NRC/NRR/DORL/LPLIV-2
| author affiliation = NRC/NRR/DORL/LPLIV-2
| addressee name =  
| addressee name =  
Line 9: Line 9:
| docket = 05000416
| docket = 05000416
| license number = NPF-029
| license number = NPF-029
| contact person = Kim J S
| contact person = Kim J
| case reference number = CAC MF4693
| case reference number = CAC MF4693
| document type = Letter, License-Operating (New/Renewal/Amendments) DKT 50
| document type = Letter, License-Operating (New/Renewal/Amendments) DKT 50
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:Vice President, Operations Entergy Operations, Inc. Grand Gulf Nuclear Station P.O. Box 756 Port Gibson, MS 39150 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 26, 2016  
{{#Wiki_filter:Vice President, Operations Entergy Operations, Inc.
Grand Gulf Nuclear Station P.O. Box 756 Port Gibson, MS 39150 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 26, 2016  


==SUBJECT:==
==SUBJECT:==
GRAND GULF NUCLEAR STATION, UNIT 1 -CORRECTION TO AMENDMENT NO. 207, RE: REQUEST FOR CHANGING FIVE TECHNICAL SPECIFICATIONS ALLOWABLE VALUES (CAC NO. MF4693)  
GRAND GULF NUCLEAR STATION, UNIT 1 - CORRECTION TO AMENDMENT NO. 207, RE: REQUEST FOR CHANGING FIVE TECHNICAL SPECIFICATIONS ALLOWABLE VALUES (CAC NO. MF4693)  


==Dear Sir or Madam:==
==Dear Sir or Madam:==
By letter dated August 31, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15195A355), the U.S. Nuclear Regulatory Commission issued Amendment No. 207 to Facility Operating License No. NPF-29 for the Grand Gulf Nuclear Station, Unit 1 (GGNS). This amendment consisted of changes to the Technical Specifications (TS) in response to Entergy Operations, lnc.'s application dated August 1, 2014 (ADAMS Accession No. ML 14216A383), as supplemented by letters dated March 3, 2015, and June 30, 2015 (ADAMS Accession Nos. ML 15063A279 and ML 15181A152, respectively).
By {{letter dated|date=August 31, 2015|text=letter dated August 31, 2015}} (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15195A355), the U.S. Nuclear Regulatory Commission issued Amendment No. 207 to Facility Operating License No. NPF-29 for the Grand Gulf Nuclear Station, Unit 1 (GGNS). This amendment consisted of changes to the Technical Specifications (TS) in response to Entergy Operations, lnc.'s application dated August 1, 2014 (ADAMS Accession No. ML14216A383), as supplemented by letters dated March 3, 2015, and June 30, 2015 (ADAMS Accession Nos. ML15063A279 and ML15181A152, respectively).
The amendment revised the following five non-conservative Technical Specification Allowable Values (AVs) in the GGNS TSs:
The amendment revised the following five non-conservative Technical Specification Allowable Values (AVs) in the GGNS TSs:
* Automatic Depressurization System Initiation Timer (TS Table 3.3.5.1-1)
Automatic Depressurization System Initiation Timer (TS Table 3.3.5.1-1)
* System A and B Containment Spray Timers (TS Table 3.3.6.3-1)
System A and B Containment Spray Timers (TS Table 3.3.6.3-1)
* Division 1and2 Degraded 4.16 kiloVolt (kV) Bus Voltage (TS Table 3.3.8.1-1)
Division 1and2 Degraded 4.16 kiloVolt (kV) Bus Voltage (TS Table 3.3.8.1-1)
* Division 3 Degraded 4.16 kV Bus Voltage (TS Table 3.3.8.1-1)
Division 3 Degraded 4.16 kV Bus Voltage (TS Table 3.3.8.1-1)
* Division 3 Degraded 4.16 kV Bus Voltage Time Delay-LOCA (Loss of Coolant Accident) (TS Table 3.3.8.1-1)
Division 3 Degraded 4.16 kV Bus Voltage Time Delay-LOCA (Loss of Coolant Accident)
Subsequent to issuance of the amendment, typographical errors were discovered on TS pages 3.3-42, 3.3-43, 3.3-66, and 3.3-79 of the amendment.
(TS Table 3.3.8.1-1)
The footnote (d), under the "Applicable Modes or Other Specified Conditions" title, was not superscripted on TS pages 3.3-42 and 3.3-43, and the letter "c" needs to be replaced with "-" in several places under the "Function" title. On TS pages 3.3-66 and 3.3-79, the letter "c" needs to be replaced with "-" in several places under the "FUNCTION" title. These corrections are editorial in nature and do not affect the previously issued safety evaluation of the amendment.
Subsequent to issuance of the amendment, typographical errors were discovered on TS pages 3.3-42, 3.3-43, 3.3-66, and 3.3-79 of the amendment. The footnote (d), under the "Applicable Modes or Other Specified Conditions" title, was not superscripted on TS pages 3.3-42 and 3.3-43, and the letter "c" needs to be replaced with "-" in several places under the "Function" title. On TS pages 3.3-66 and 3.3-79, the letter "c" needs to be replaced with "-"
In addition, TS page 3.3-79, regarding Division 3-4.16 kV Emergency Bus Undervoltage, Degraded Voltage -Time Delay, LOCA (TS Table 3.3.8.1-1 (Item 2.e)), new AV of 3.68 seconds was not revised on the Table 3.3.8.1-1 (Item 2.e). In the safety evaluation of the amendment, the NRC staff evaluated and confirmed a proposed AV of 3.68 seconds for the Division 3 Degraded 4.16 kV Bus Voltage time delay. Enclosed are the revised TS pages 3.3-42, 3.3-43, 3.3-66, and 3.3-79. If you have any questions regarding this matter, please contact me at 301-415-4125 or by e-mail at James.Kim@nrc.gov.
in several places under the "FUNCTION" title. These corrections are editorial in nature and do not affect the previously issued safety evaluation of the amendment.
In addition, TS page 3.3-79, regarding Division 3-4.16 kV Emergency Bus Undervoltage, Degraded Voltage - Time Delay, LOCA (TS Table 3.3.8.1-1 (Item 2.e)), new AV of 3.68 seconds was not revised on the Table 3.3.8.1-1 (Item 2.e). In the safety evaluation of the amendment, the NRC staff evaluated and confirmed a proposed AV of 3.68 seconds for the Division 3 Degraded 4.16 kV Bus Voltage time delay.
Enclosed are the revised TS pages 3.3-42, 3.3-43, 3.3-66, and 3.3-79. If you have any questions regarding this matter, please contact me at 301-415-4125 or by e-mail at James.Kim@nrc.gov.
Docket No. 50-416  
Docket No. 50-416  


==Enclosure:==
==Enclosure:==
Corrected TS pages 3.3-42, 3.3-43, 3.3-66 3.3-79 for Amendment No. 207 cc w/encl: Distribution via Listserv Sincerely, James Kim, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation


Corrected TS pages 3.3-42, 3.3-43, 3.3-66 3.3-79 for Amendment No. 207 cc w/encl: Distribution via Listserv Sincerely, James Kim, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 4 of 5) Emergency Core Cooling System Instrumentation FUNCTION 4. Automatic Depressurization System (ADS) Trip System A APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION a. Reactor Vessel l,2(d) ,3(d) 2 Water Level -Low Low Low, Level 1 b. Drywell 1,2(d) ,3(d) 2 Pressure -High c. ADS Initiation 1,2(d) ,3(d) 1 Timer d. Reactor Vessel 1,2(d) ,3(d) 1 Water Level -Low, Level 3 (Confirmatory)
ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 4 of 5)
: e. LPCS Pump l,2(d) ,3(d) 2 Discharge Pressure -High f. LPCI Pump A l,2(d),3(d) 2 Discharge Pressure -High g. ADS Bypass l,2(d) ,3(d) 2 Timer (High Drywell Pressure)
Emergency Core Cooling System Instrumentation FUNCTION
: h. Manual l,2(d),3(d) 2/system Initiation CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 F F G F G G G G (d) With reactor steam dome pressure > 150 psig. GRAND GULF 3.3-42 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE SR 3.3.5.1.1 2 -152.5 inches SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.1 s 1.44 psig SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.2 s 115 seconds SR 3.3.5.1.4 SR 3.3.5.1.6 SR 3 . 3 . 5 . 1 . 1 2 10. 8 inches SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3. 3. 5. 1. 1 2 125 psig and SR 3.3.5.1.2 s 165 psig SR 3 . 3 . 5 .
: 4. Automatic Depressurization System (ADS)
: 1. 3 SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.1 2 115 psig and SR 3.3.5.1.2 s 135 psig SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3. 3. 5. 1. 2 s 9. 4 minutes SR 3.3.5.1.4 SR 3.3.5.1.6 SR 3. 3 . 5. 1 . 6 NA (continued)
Trip System A APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION
Amendment No. 207 ECCS Instrumentation 3.3.5. I Table 3.3.5.1-1 (page 5 of 5) Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE 5. ADS Trip System B a. Reactor Vessel 1,2(d),3(d) 2 F SR 3.3.5.1.1 2 -152.5 Water Level -Low SR 3.3.5.1.2 inches Low Low, Level 1 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6
: a. Reactor Vessel l,2(d),3(d) 2 Water Level -
: b. Drywell Pressure -1,2(d),3(d) 2 F SR 3.3.5.1.1
Low Low Low, Level 1
: b. Drywell 1,2(d),3(d) 2 Pressure - High
: c. ADS Initiation 1,2(d),3(d) 1 Timer
: d. Reactor Vessel 1,2(d),3(d) 1 Water Level -
Low, Level 3 (Confirmatory)
: e. LPCS Pump l,2(d),3(d) 2 Discharge Pressure - High
: f. LPCI Pump A l,2(d),3(d) 2 Discharge Pressure - High
: g. ADS Bypass l,2(d),3(d) 2 Timer (High Drywell Pressure)
: h. Manual l,2(d),3(d) 2/system Initiation CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 F
F G
F G
G G
G (d) With reactor steam dome pressure > 150 psig.
GRAND GULF 3.3-42 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE SR 3.3.5.1.1 2 -152.5 inches SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.1 s 1.44 psig SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.2 s 115 seconds SR 3.3.5.1.4 SR 3.3.5.1.6 SR 3. 3. 5. 1. 1 2 10. 8 inches SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 SR
: 3. 3. 5. 1. 1 2 125 psig and SR 3.3.5.1.2 s 165 psig SR 3. 3. 5. 1. 3 SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.1 2 115 psig and SR 3.3.5.1.2 s 135 psig SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 SR
: 3. 3. 5. 1. 2 s 9. 4 minutes SR 3.3.5.1.4 SR 3.3.5.1.6 SR
: 3. 3. 5. 1. 6 NA (continued)
Amendment No. ~. 207  
 
ECCS Instrumentation 3.3.5. I Table 3.3.5.1-1 (page 5 of 5)
Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE
: 5. ADS Trip System B
: a. Reactor Vessel 1,2(d),3(d) 2 F
SR 3.3.5.1.1 2 -152.5 Water Level - Low SR 3.3.5.1.2 inches Low Low, Level 1 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6
: b. Drywell Pressure -
1,2(d),3(d) 2 F
SR 3.3.5.1.1
::;; 1. 44 psig High SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6
::;; 1. 44 psig High SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6
: c. ADS Initiation 1,2(d) ,3(d) 1 G SR 3.3.5.1.2
: c. ADS Initiation 1,2(d),3(d) 1 G
::;; 115 seconds! Timer SR 3.3.5.1.4 SR 3.3.5.1.6
SR 3.3.5.1.2
: d. Reactor Vessel 1,2(d),3(d) 1 F SR 3.3.5.1.1 2 10.8 inches Water Level -SR 3.3.5.1.2 Low, Level 3 SR 3.3.5.1.3 (Confirmatory)
::;; 115 seconds!
Timer SR 3.3.5.1.4 SR 3.3.5.1.6
: d. Reactor Vessel 1,2(d),3(d) 1 F
SR 3.3.5.1.1 2 10.8 inches Water Level -
SR 3.3.5.1.2 Low, Level 3 SR 3.3.5.1.3 (Confirmatory)
SR 3.3.5.1.5 SR 3.3.5.1.6
SR 3.3.5.1.5 SR 3.3.5.1.6
: e. LPCI Pumps B & c 1,2(d) ,3(d) 2 per G SR 3.3.5.1.1 2 115 psig Discharge pump SR 3.3.5.1.2 and Pressure -High SR 3.3.5.1.3
: e. LPCI Pumps B & c 1,2(d),3(d) 2 per G
SR 3.3.5.1.1 2 115 psig Discharge pump SR 3.3.5.1.2 and Pressure -High SR 3.3.5.1.3
::;; 135 psig SR 3.3.5.1.5 SR 3.3.5.1.6
::;; 135 psig SR 3.3.5.1.5 SR 3.3.5.1.6
: f. ADS Bygass Timer 1,2(d),3(d) 2 G SR 3.3.5.1.2
: f. ADS Bygass Timer 1,2(d),3(d) 2 G
SR 3.3.5.1.2
::;; 9. 4 minutes (High rywell SR 3.3.5.1.4 Pressure SR 3.3.5.1.6
::;; 9. 4 minutes (High rywell SR 3.3.5.1.4 Pressure SR 3.3.5.1.6
: g. Manual Initiation 1,2(d) ,3(d) 2/system G SR 3.3.5.1.6 NA (d) With reactor steam dome pressure > 150 psig. GRAND GULF 3.3-43 Amendment No. 207 RHR Containment Spray System Instrumentation 3.3.6.3 Table 3.3.6.3-1 (page 1 of 1) RHR Containment Spray System Instrumentation FUNCTION 1. Drywell Pressure -High 2. Containment Pressure-High
: g. Manual Initiation 1,2(d),3(d) 2/system G
: 3. Reactor Vessel Water Level-Low Low Low, Level 1 4. System A and System B Timers GRAND GULF REQUIRED CHANNELS PER TRIP SYSTEM 2 1 2 CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 B c B 1 c SURVEILLANCE REQUIREMENTS SR 3.3.6.3.1 SR 3.3.6.3.2 SR 3.3.6.3.3 SR 3.3.6.3.5 SR 3.3.6.3.6 SR 3.3.6.3.1 SR 3.3.6.3.2 SR 3.3.6.3.3 SR 3.3.6.3.5 SR 3.3.6.3.6 SR 3.3.6.3.1 SR 3.3.6.3.2 SR 3.3.6.3.3 SR 3.3.6.3.5 SR 3.3.6.3.6 SR 3.3.6.3.2 SR 3.3.6.3.4 SR 3.3.6.3.6
SR 3.3.5.1.6 NA (d) With reactor steam dome pressure > 150 psig.
::::: ::::: ;;::: ;;::: ::::: ALLOWABLE VALUE 1.44 psig 8.34 psig -152.5 inches 10.6 minutes 11. 1 minutes and 3.3-66 Amendment No. 207
GRAND GULF 3.3-43 Amendment No. ~. 207  
: 1. 2. Table 3.3.8.1-1 (page 1 of 1) Loss of Power Instrumentation FUNCTION Divisions 1 and 2 -4.16 kV Emergency Bus Undervoltage
 
: a. Loss of Voltage -4.16 kV basis b. Loss of Voltage -Time Delay c. Degraded Voltage -4.16 kV basis d. Degraded Voltage -Time Delay Division 3 -4.16 kV Emergency Bus Undervoltage
RHR Containment Spray System Instrumentation 3.3.6.3 Table 3.3.6.3-1 (page 1 of 1)
: a. Loss of Voltage -4.16 kV basis b. Loss of Voltage -Time Delay c. Degraded Voltage -4.16 kV basis d. Degraded Voltage -Time Delay, No LOCA e. Degraded Voltage -Time Delay, LOCA REQUIRED CHANNELS PER DIVISION 4 2 4 2 4 2 4 2 4 SURVEILLANCE REQUIREMENTS SR 3.3.8.1.1 SR 3.3.8.1.2 SR 3.3.8.1.4 SR 3.3.8.1.3 SR 3.3.8.1.4 SR 3.3.8.1.1 SR 3.3.8.1.2 SR 3.3.8.1.4 SR 3.3.8.1.3 SR 3.3.8.1.4 SR 3.3.8.1.3 SR 3.3.8.1.4 SR 3.3.8.1.3 SR 3.3.8.1.4 SR 3.3.8.1.3 SR 3.3.8.1.4 SR 3.3.8.1.3 SR 3.3.8.1.4 SR 3.3.8.1.3 SR 3.3.8.1.4 GRAND GULF 3.3-79 LOP Instrumentation 3.3.8.1 ALLOWABLE VALUE ;::2621 V and 5 2912 v ;::0.4 seconds and 51.0 seconds ;::3764.25 V and 53837.6 V ;::8.5 seconds and 59.5 seconds ;::2984 V and 53106 V ;::2.0 seconds and 52.5 seconds ;::3605 V and 53763.5 v ;::4. 5 minutes and 55.5 minutes ;::3.68 seconds and 54.4 seconds Amendment No. H-B-, -3:-9--9--;-
RHR Containment Spray System Instrumentation FUNCTION
207   Enclosed are the revised TS pages 3.3-42, 3.3-43, 3.3-66, and 3.3-79. If you have any questions regarding this matter, please contact me at 301-415-4125 or by e-mail at James.Kim@nrc.gov.
: 1. Drywell Pressure -
High
: 2. Containment Pressure-High
: 3. Reactor Vessel Water Level-Low Low Low, Level 1
: 4. System A and System B Timers GRAND GULF REQUIRED CHANNELS PER TRIP SYSTEM 2
1 2
CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 B
c B
1 c
SURVEILLANCE REQUIREMENTS SR 3.3.6.3.1 SR 3.3.6.3.2 SR 3.3.6.3.3 SR 3.3.6.3.5 SR 3.3.6.3.6 SR 3.3.6.3.1 SR 3.3.6.3.2 SR 3.3.6.3.3 SR 3.3.6.3.5 SR 3.3.6.3.6 SR 3.3.6.3.1 SR 3.3.6.3.2 SR 3.3.6.3.3 SR 3.3.6.3.5 SR 3.3.6.3.6 SR 3.3.6.3.2 SR 3.3.6.3.4 SR 3.3.6.3.6 ALLOWABLE VALUE 1.44 psig 8.34 psig  
-152.5 inches 10.6 minutes
: 11. 1 minutes and 3.3-66 Amendment No. ~. 207
: 1.
: 2.
Table 3.3.8.1-1 (page 1 of 1)
Loss of Power Instrumentation FUNCTION Divisions 1 and 2 -
4.16 kV Emergency Bus Undervoltage
: a. Loss of Voltage - 4.16 kV basis
: b. Loss of Voltage - Time Delay
: c. Degraded Voltage - 4.16 kV basis
: d. Degraded Voltage - Time Delay Division 3 - 4.16 kV Emergency Bus Undervoltage
: a. Loss of Voltage - 4.16 kV basis
: b. Loss of Voltage -
Time Delay
: c. Degraded Voltage - 4.16 kV basis
: d. Degraded Voltage - Time Delay, No LOCA
: e. Degraded Voltage - Time Delay, LOCA REQUIRED CHANNELS PER DIVISION 4
2 4
2 4
2 4
2 4
SURVEILLANCE REQUIREMENTS SR 3.3.8.1.1 SR 3.3.8.1.2 SR 3.3.8.1.4 SR 3.3.8.1.3 SR 3.3.8.1.4 SR 3.3.8.1.1 SR 3.3.8.1.2 SR 3.3.8.1.4 SR 3.3.8.1.3 SR 3.3.8.1.4 SR 3.3.8.1.3 SR 3.3.8.1.4 SR 3.3.8.1.3 SR 3.3.8.1.4 SR 3.3.8.1.3 SR 3.3.8.1.4 SR 3.3.8.1.3 SR 3.3.8.1.4 SR 3.3.8.1.3 SR 3.3.8.1.4 GRAND GULF 3.3-79 LOP Instrumentation 3.3.8.1 ALLOWABLE VALUE  
;::2621 V and 5 2912 v  
;::0.4 seconds and 51.0 seconds  
;::3764.25 V and 53837.6 V  
;::8.5 seconds and 59.5 seconds  
;::2984 V and 53106 V  
;::2.0 seconds and 52.5 seconds  
;::3605 V and 53763.5 v  
;::4. 5 minutes and 55.5 minutes  
;::3.68 seconds and 54.4 seconds Amendment No. H-B-,  
-3:-9--9--;- 207 Enclosed are the revised TS pages 3.3-42, 3.3-43, 3.3-66, and 3.3-79. If you have any questions regarding this matter, please contact me at 301-415-4125 or by e-mail at James.Kim@nrc.gov.
Docket No. 50-416  
Docket No. 50-416  


==Enclosure:==
==Enclosure:==
Corrected TS pages 3.3-42, 3.3-43, 3.3-66 3.3-79 for Amendment No. 207 cc w/encl: Distribution via Listserv DISTRIBUTION:
Corrected TS pages 3.3-42, 3.3-43, 3.3-66 3.3-79 for Amendment No. 207 cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL4-2 R/F RidsACRS_MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDorllpl4-2 Resource RidsNrrLAPBlechman Resource RidsNrrPMGrandGulf Resource RidsRgn4MailCenter Resource ADAMS Accession No.: ML 16132A194 Sincerely, IRA/ James Kim, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation OFFICE DORL/LPL4-2/PM DORL/LPL4-2/LA DORL/LPL4-2/BC DORL/LPL4-2/PM NAME JKim PBlechman MKhanna JKim DATE 5/25/2016 5/25/2016 5/25/2016 5/26/2016 OFFICIAL AGENCY RECORD}}
PUBLIC LPL4-2 R/F RidsACRS_MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDorllpl4-2 Resource RidsNrrLAPBlechman Resource RidsNrrPMGrandGulf Resource RidsRgn4MailCenter Resource ADAMS Accession No.: ML16132A194 Sincerely, IRA/
James Kim, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation OFFICE DORL/LPL4-2/PM DORL/LPL4-2/LA DORL/LPL4-2/BC DORL/LPL4-2/PM NAME JKim PBlechman MKhanna JKim DATE 5/25/2016 5/25/2016 5/25/2016 5/26/2016 OFFICIAL AGENCY RECORD}}

Latest revision as of 00:07, 10 January 2025

Correction to Amendment No. 207, Request for Changing Five Technical Specifications Allowable Levels
ML16132A194
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 05/26/2016
From: James Kim
Plant Licensing Branch IV
To:
Entergy Operations
Kim J
References
CAC MF4693
Download: ML16132A194 (7)
v • d • e


Text

Vice President, Operations Entergy Operations, Inc.

Grand Gulf Nuclear Station P.O. Box 756 Port Gibson, MS 39150 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 26, 2016

SUBJECT:

GRAND GULF NUCLEAR STATION, UNIT 1 - CORRECTION TO AMENDMENT NO. 207, RE: REQUEST FOR CHANGING FIVE TECHNICAL SPECIFICATIONS ALLOWABLE VALUES (CAC NO. MF4693)

Dear Sir or Madam:

By letter dated August 31, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15195A355), the U.S. Nuclear Regulatory Commission issued Amendment No. 207 to Facility Operating License No. NPF-29 for the Grand Gulf Nuclear Station, Unit 1 (GGNS). This amendment consisted of changes to the Technical Specifications (TS) in response to Entergy Operations, lnc.'s application dated August 1, 2014 (ADAMS Accession No. ML14216A383), as supplemented by letters dated March 3, 2015, and June 30, 2015 (ADAMS Accession Nos. ML15063A279 and ML15181A152, respectively).

The amendment revised the following five non-conservative Technical Specification Allowable Values (AVs) in the GGNS TSs:

Automatic Depressurization System Initiation Timer (TS Table 3.3.5.1-1)

System A and B Containment Spray Timers (TS Table 3.3.6.3-1)

Division 1and2 Degraded 4.16 kiloVolt (kV) Bus Voltage (TS Table 3.3.8.1-1)

Division 3 Degraded 4.16 kV Bus Voltage (TS Table 3.3.8.1-1)

Division 3 Degraded 4.16 kV Bus Voltage Time Delay-LOCA (Loss of Coolant Accident)

(TS Table 3.3.8.1-1)

Subsequent to issuance of the amendment, typographical errors were discovered on TS pages 3.3-42, 3.3-43, 3.3-66, and 3.3-79 of the amendment. The footnote (d), under the "Applicable Modes or Other Specified Conditions" title, was not superscripted on TS pages 3.3-42 and 3.3-43, and the letter "c" needs to be replaced with "-" in several places under the "Function" title. On TS pages 3.3-66 and 3.3-79, the letter "c" needs to be replaced with "-"

in several places under the "FUNCTION" title. These corrections are editorial in nature and do not affect the previously issued safety evaluation of the amendment.

In addition, TS page 3.3-79, regarding Division 3-4.16 kV Emergency Bus Undervoltage, Degraded Voltage - Time Delay, LOCA (TS Table 3.3.8.1-1 (Item 2.e)), new AV of 3.68 seconds was not revised on the Table 3.3.8.1-1 (Item 2.e). In the safety evaluation of the amendment, the NRC staff evaluated and confirmed a proposed AV of 3.68 seconds for the Division 3 Degraded 4.16 kV Bus Voltage time delay.

Enclosed are the revised TS pages 3.3-42, 3.3-43, 3.3-66, and 3.3-79. If you have any questions regarding this matter, please contact me at 301-415-4125 or by e-mail at James.Kim@nrc.gov.

Docket No. 50-416

Enclosure:

Corrected TS pages 3.3-42, 3.3-43, 3.3-66 3.3-79 for Amendment No. 207 cc w/encl: Distribution via Listserv Sincerely, James Kim, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 4 of 5)

Emergency Core Cooling System Instrumentation FUNCTION

4. Automatic Depressurization System (ADS)

Trip System A APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION

a. Reactor Vessel l,2(d),3(d) 2 Water Level -

Low Low Low, Level 1

b. Drywell 1,2(d),3(d) 2 Pressure - High
c. ADS Initiation 1,2(d),3(d) 1 Timer
d. Reactor Vessel 1,2(d),3(d) 1 Water Level -

Low, Level 3 (Confirmatory)

e. LPCS Pump l,2(d),3(d) 2 Discharge Pressure - High
f. LPCI Pump A l,2(d),3(d) 2 Discharge Pressure - High
g. ADS Bypass l,2(d),3(d) 2 Timer (High Drywell Pressure)
h. Manual l,2(d),3(d) 2/system Initiation CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 F

F G

F G

G G

G (d) With reactor steam dome pressure > 150 psig.

GRAND GULF 3.3-42 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE SR 3.3.5.1.1 2 -152.5 inches SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.1 s 1.44 psig SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.2 s 115 seconds SR 3.3.5.1.4 SR 3.3.5.1.6 SR 3. 3. 5. 1. 1 2 10. 8 inches SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 SR

3. 3. 5. 1. 1 2 125 psig and SR 3.3.5.1.2 s 165 psig SR 3. 3. 5. 1. 3 SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.1 2 115 psig and SR 3.3.5.1.2 s 135 psig SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 SR
3. 3. 5. 1. 2 s 9. 4 minutes SR 3.3.5.1.4 SR 3.3.5.1.6 SR
3. 3. 5. 1. 6 NA (continued)

Amendment No. ~. 207

ECCS Instrumentation 3.3.5. I Table 3.3.5.1-1 (page 5 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

5. ADS Trip System B
a. Reactor Vessel 1,2(d),3(d) 2 F

SR 3.3.5.1.1 2 -152.5 Water Level - Low SR 3.3.5.1.2 inches Low Low, Level 1 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6

b. Drywell Pressure -

1,2(d),3(d) 2 F

SR 3.3.5.1.1

1. 44 psig High SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6
c. ADS Initiation 1,2(d),3(d) 1 G

SR 3.3.5.1.2

115 seconds!

Timer SR 3.3.5.1.4 SR 3.3.5.1.6

d. Reactor Vessel 1,2(d),3(d) 1 F

SR 3.3.5.1.1 2 10.8 inches Water Level -

SR 3.3.5.1.2 Low, Level 3 SR 3.3.5.1.3 (Confirmatory)

SR 3.3.5.1.5 SR 3.3.5.1.6

e. LPCI Pumps B & c 1,2(d),3(d) 2 per G

SR 3.3.5.1.1 2 115 psig Discharge pump SR 3.3.5.1.2 and Pressure -High SR 3.3.5.1.3

135 psig SR 3.3.5.1.5 SR 3.3.5.1.6
f. ADS Bygass Timer 1,2(d),3(d) 2 G

SR 3.3.5.1.2

9. 4 minutes (High rywell SR 3.3.5.1.4 Pressure SR 3.3.5.1.6
g. Manual Initiation 1,2(d),3(d) 2/system G

SR 3.3.5.1.6 NA (d) With reactor steam dome pressure > 150 psig.

GRAND GULF 3.3-43 Amendment No. ~. 207

RHR Containment Spray System Instrumentation 3.3.6.3 Table 3.3.6.3-1 (page 1 of 1)

RHR Containment Spray System Instrumentation FUNCTION

1. Drywell Pressure -

High

2. Containment Pressure-High
3. Reactor Vessel Water Level-Low Low Low, Level 1
4. System A and System B Timers GRAND GULF REQUIRED CHANNELS PER TRIP SYSTEM 2

1 2

CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 B

c B

1 c

SURVEILLANCE REQUIREMENTS SR 3.3.6.3.1 SR 3.3.6.3.2 SR 3.3.6.3.3 SR 3.3.6.3.5 SR 3.3.6.3.6 SR 3.3.6.3.1 SR 3.3.6.3.2 SR 3.3.6.3.3 SR 3.3.6.3.5 SR 3.3.6.3.6 SR 3.3.6.3.1 SR 3.3.6.3.2 SR 3.3.6.3.3 SR 3.3.6.3.5 SR 3.3.6.3.6 SR 3.3.6.3.2 SR 3.3.6.3.4 SR 3.3.6.3.6 ALLOWABLE VALUE 1.44 psig 8.34 psig

-152.5 inches 10.6 minutes

11. 1 minutes and 3.3-66 Amendment No. ~. 207
1.
2.

Table 3.3.8.1-1 (page 1 of 1)

Loss of Power Instrumentation FUNCTION Divisions 1 and 2 -

4.16 kV Emergency Bus Undervoltage

a. Loss of Voltage - 4.16 kV basis
b. Loss of Voltage - Time Delay
c. Degraded Voltage - 4.16 kV basis
d. Degraded Voltage - Time Delay Division 3 - 4.16 kV Emergency Bus Undervoltage
a. Loss of Voltage - 4.16 kV basis
b. Loss of Voltage -

Time Delay

c. Degraded Voltage - 4.16 kV basis
d. Degraded Voltage - Time Delay, No LOCA
e. Degraded Voltage - Time Delay, LOCA REQUIRED CHANNELS PER DIVISION 4

2 4

2 4

2 4

2 4

SURVEILLANCE REQUIREMENTS SR 3.3.8.1.1 SR 3.3.8.1.2 SR 3.3.8.1.4 SR 3.3.8.1.3 SR 3.3.8.1.4 SR 3.3.8.1.1 SR 3.3.8.1.2 SR 3.3.8.1.4 SR 3.3.8.1.3 SR 3.3.8.1.4 SR 3.3.8.1.3 SR 3.3.8.1.4 SR 3.3.8.1.3 SR 3.3.8.1.4 SR 3.3.8.1.3 SR 3.3.8.1.4 SR 3.3.8.1.3 SR 3.3.8.1.4 SR 3.3.8.1.3 SR 3.3.8.1.4 GRAND GULF 3.3-79 LOP Instrumentation 3.3.8.1 ALLOWABLE VALUE

2621 V and 5 2912 v
0.4 seconds and 51.0 seconds
3764.25 V and 53837.6 V
8.5 seconds and 59.5 seconds
2984 V and 53106 V
2.0 seconds and 52.5 seconds
3605 V and 53763.5 v
4. 5 minutes and 55.5 minutes
3.68 seconds and 54.4 seconds Amendment No. H-B-,

-3:-9--9--;- 207 Enclosed are the revised TS pages 3.3-42, 3.3-43, 3.3-66, and 3.3-79. If you have any questions regarding this matter, please contact me at 301-415-4125 or by e-mail at James.Kim@nrc.gov.

Docket No. 50-416

Enclosure:

Corrected TS pages 3.3-42, 3.3-43, 3.3-66 3.3-79 for Amendment No. 207 cc w/encl: Distribution via Listserv DISTRIBUTION:

PUBLIC LPL4-2 R/F RidsACRS_MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDorllpl4-2 Resource RidsNrrLAPBlechman Resource RidsNrrPMGrandGulf Resource RidsRgn4MailCenter Resource ADAMS Accession No.: ML16132A194 Sincerely, IRA/

James Kim, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation OFFICE DORL/LPL4-2/PM DORL/LPL4-2/LA DORL/LPL4-2/BC DORL/LPL4-2/PM NAME JKim PBlechman MKhanna JKim DATE 5/25/2016 5/25/2016 5/25/2016 5/26/2016 OFFICIAL AGENCY RECORD

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