ML15289A063

From kanterella
Jump to navigation Jump to search
Revision 151 to SMC-LC-16.5.1, Inventory Control - Reduced Inventory Operation.
ML15289A063
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 10/03/2015
From:
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
SMC-LC-16.5.1, Rev 151
Download: ML15289A063 (5)
v • d • e


Text

Date: 1013/2015 Distribution: Duke Energy Document Transmittal #: TR-NUC-MC-O00936

1. Beaver, Bonnie C
2. Carroll, Michael E DOCUMENT TRANSMI1TAL FORM

Purpose:

Issue

3. Dacus, Casey Michelle Released By:

Facility: MCGUIRE NUCLEAR STATION Duke Enerqy

4. Gardner, Troy R
5. Helton, Daniel E SUBJECT 13225 Haaers Ferr, Road
6. Mc Ginnis, Vickie L (At Mcguire) MC-SLC-16.5.1 Document Manaqiement
7. McCree, Victor M MG02M
8. MCG DOc CNTRL MISC MAN Huntersville, NC 28078
9. MCG OPS PROCEDURE GP M NSDCRM~duke-enerqy.com
10. MCG OPS STAFF MGR
11. MCG PLANT ENG. LIBR.
12. Miller, Don
13. Montgomery, Gary L
14. OPS HUMAN PERFORMANCE -
15. OPS TRNG MGR.
16. RESIDENT NRC INSPECT
17. SERV BLDG FILE ROOM -
18. Spencer, William C
19. U S NUC REG WASHINGTON, DC
20. USNRC Page 1 of 1 jIC*N - M - MNS-SLC-165.1- 1 ISSUE* F IIEFYII FYIIEEFYIE FEIIE FYIIE FlYII FYIEEYIIEEFYIEEFYIIE FYIIEIFYIIEIFYIIEIFYIIE R&AI FYIIE FYIIEIR&AI R&AII Remarks: Revision 151 to MC-SLC-16,5.1

Inventory Control-Reduced Inventory Operation 16.5.1 16.5 REACTOR COOLANT SYSTEM (RCS) 16.5.1 Inventory Control-Reduced Inventory Operation COMMITMENT A detailed review of each outage schedule that involves operation at reduced inventory shall be conducted looking at evolutions which could perturb the RCS.

AND The RCS shall be properly vented when steam generator nozzle dams are in use or the RCS cold leg is open > 1 in2.

AND The reactor shall be subcritical for. at least 7 days, or as specified in Design Study CNDS-0242, or MGDS-0228/CNDS-0218.

-~~~~NOTE---- - - -

Activities that could perturb the RCS during reduced inventory operation shall require prior notification of the operations shift manager.

APPLICABILITY RCS level < 60 inches (wide range) with irradiated fuel in the core.

REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Steam Generator nozzle A.1 Initiate action to provide the Immediately dams are in use and required hot leg vent path.

RCS not properly vented.

AND A.2 Suspend all activities that Immediately could perturb RCS level or which may reduce the reliability of the operating RHR loop.

Mc(3uire Units 1 and 2165-1Rvso11 16.5.1-1 Revision 151

Inventory Control-Reduced Inventory Operation 16.5.1 B. RCS 2cold leg is open B.1 Initiate action to provide the Immediately

_>1 in and RCS not required hot leg vent path.

properly vented.

AND NOTE---

This Condition does not B.2 Suspend all activities that Immediately apply ifthe cold leg could perturb RCS level or opening can be which may reduce the re-closed prior to reliability of the operating pressurizing the RCS, RHR loop.

boiling, or losing RCS inventory through this opening due to RCS heatup or expansion following a loss of RHR cooling event.

TESTING REQUIREMENTS None BASES Generic Letter 88-17 and NU REG 1410 involve concerns associated with a loss of Residual Heat Removal (RHR) during RCS reduced inventory. Numerous events have occurred in the industry that resulted in a loss of RHR during reduced inventory operation. This is of great concern due to the potential for substantial core damage occurring in a relatively short time period. This SLC depicts those commitments that are extremely important to nuclear safety, however, are not presently covered by Technical Specifications.

Under the stated APPLICABILITY, if the steam generator nozzle dams are installed OR the RCS cold leg piping is opened with total opening of one square inch or greater, then a hot leg vent path is required. The hot leg vent path is not required for the cold leg opening ifadequate controls are in place that will re-close the cold leg opening prior to reaching any of the conditions listed below due to loss of RHR cooling. An engineering evaluation should be performed to determine the following:

1. time to boil,
2. time to lose inventory due to heatup or expansion of RCS to the open location, and
3. time to pressurization of the RCS.

The controls should be proceduralized and consist of stationing a dedicated individual at the opening who is in continuous communication with the operators in the control room. This individual will have a method to re-close the opening prior to reaching any of the conditions above due to loss of RHR cooling. By taking action to re-close the opening, inventory will not be lost.

McGuire Units 1 and 2165-2Rvso11 16.5.1-2 Revision 151

Inventory Control-Reduced Inventory Operation 16.5.1 BASES Continued The vent path may be satisfied by:

1. Hot leg nozzle dam not installed on the vented loop AND Removal of either of the following on the vented loop:
a. Hot leg diaphragm and manway OR
b. Cold leg diaphragm and manway (with associated coid leg nozzle dam installed*)

OR

2. Reactor vessel head is removed.
  • Installation of the associated cold leg nozzle dam avoids diversion of makeup flow (injected via a cold leg nozzle) intended for the core.

McGuire Units 1 and 216513Rvio11 16.5.1-3 Revision 151

Inventory Control-Reduced Inventory Operation 16.

5.1 REFERENCES

1. Generic Letter 88-17, Loss of Decay Heat Removal
2. NUREG 1410, Loss of Vital AC Power and Residual Heat Removal During Mid-Loop Operation at Vogtle Nuclear Station.
3. Integrated Scheduling Management Procedure 3.1, Outage Planning and Execution Responsibilities
4. McGuire Nuclear Station responses to GL 88-17, dated January 3, 1989, February 2, 1989, March 10, 1989 and February 24, 1993.
5. Nuclear Station Directive NSD-403, Shutdown Risk Management (Modes 4, 5, 6, and No-Mode) per 10 CFR 50. 65(a)(4).
6. Design Study CNDS-0242, Catawba and McGuire Nuclear Stations, Shutdown By Decay Heat Level Before Mid-Loop Operation, Safety Analysis, Nuclear Engineering, Nuclear Services.
7. Design Study MGDS-0228/CNDS-0218, McGuire/Catawba Nuclear Stations, Loss of Decay Heat Removal With Steam Generator Mitigation, Safety Analysis, Engineering Support Section, Design Engineering Department.
8. PIP M-08-05725.
9. PIP M-09-04863.
10. PIPs M-1 4-1 0887, and M-14-1 0888.

McGuire Units 1 and 216514Rvso11 16.5.1-4 Revision 151

Date: 1013/2015 Distribution: Duke Energy Document Transmittal #: TR-NUC-MC-O00936

1. Beaver, Bonnie C
2. Carroll, Michael E DOCUMENT TRANSMI1TAL FORM

Purpose:

Issue

3. Dacus, Casey Michelle Released By:

Facility: MCGUIRE NUCLEAR STATION Duke Enerqy

4. Gardner, Troy R
5. Helton, Daniel E SUBJECT 13225 Haaers Ferr, Road
6. Mc Ginnis, Vickie L (At Mcguire) MC-SLC-16.5.1 Document Manaqiement
7. McCree, Victor M MG02M
8. MCG DOc CNTRL MISC MAN Huntersville, NC 28078
9. MCG OPS PROCEDURE GP M NSDCRM~duke-enerqy.com
10. MCG OPS STAFF MGR
11. MCG PLANT ENG. LIBR.
12. Miller, Don
13. Montgomery, Gary L
14. OPS HUMAN PERFORMANCE -
15. OPS TRNG MGR.
16. RESIDENT NRC INSPECT
17. SERV BLDG FILE ROOM -
18. Spencer, William C
19. U S NUC REG WASHINGTON, DC
20. USNRC Page 1 of 1 jIC*N - M - MNS-SLC-165.1- 1 ISSUE* F IIEFYII FYIIEEFYIE FEIIE FYIIE FlYII FYIEEYIIEEFYIEEFYIIE FYIIEIFYIIEIFYIIEIFYIIE R&AI FYIIE FYIIEIR&AI R&AII Remarks: Revision 151 to MC-SLC-16,5.1

Inventory Control-Reduced Inventory Operation 16.5.1 16.5 REACTOR COOLANT SYSTEM (RCS) 16.5.1 Inventory Control-Reduced Inventory Operation COMMITMENT A detailed review of each outage schedule that involves operation at reduced inventory shall be conducted looking at evolutions which could perturb the RCS.

AND The RCS shall be properly vented when steam generator nozzle dams are in use or the RCS cold leg is open > 1 in2.

AND The reactor shall be subcritical for. at least 7 days, or as specified in Design Study CNDS-0242, or MGDS-0228/CNDS-0218.

-~~~~NOTE---- - - -

Activities that could perturb the RCS during reduced inventory operation shall require prior notification of the operations shift manager.

APPLICABILITY RCS level < 60 inches (wide range) with irradiated fuel in the core.

REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Steam Generator nozzle A.1 Initiate action to provide the Immediately dams are in use and required hot leg vent path.

RCS not properly vented.

AND A.2 Suspend all activities that Immediately could perturb RCS level or which may reduce the reliability of the operating RHR loop.

Mc(3uire Units 1 and 2165-1Rvso11 16.5.1-1 Revision 151

Inventory Control-Reduced Inventory Operation 16.5.1 B. RCS 2cold leg is open B.1 Initiate action to provide the Immediately

_>1 in and RCS not required hot leg vent path.

properly vented.

AND NOTE---

This Condition does not B.2 Suspend all activities that Immediately apply ifthe cold leg could perturb RCS level or opening can be which may reduce the re-closed prior to reliability of the operating pressurizing the RCS, RHR loop.

boiling, or losing RCS inventory through this opening due to RCS heatup or expansion following a loss of RHR cooling event.

TESTING REQUIREMENTS None BASES Generic Letter 88-17 and NU REG 1410 involve concerns associated with a loss of Residual Heat Removal (RHR) during RCS reduced inventory. Numerous events have occurred in the industry that resulted in a loss of RHR during reduced inventory operation. This is of great concern due to the potential for substantial core damage occurring in a relatively short time period. This SLC depicts those commitments that are extremely important to nuclear safety, however, are not presently covered by Technical Specifications.

Under the stated APPLICABILITY, if the steam generator nozzle dams are installed OR the RCS cold leg piping is opened with total opening of one square inch or greater, then a hot leg vent path is required. The hot leg vent path is not required for the cold leg opening ifadequate controls are in place that will re-close the cold leg opening prior to reaching any of the conditions listed below due to loss of RHR cooling. An engineering evaluation should be performed to determine the following:

1. time to boil,
2. time to lose inventory due to heatup or expansion of RCS to the open location, and
3. time to pressurization of the RCS.

The controls should be proceduralized and consist of stationing a dedicated individual at the opening who is in continuous communication with the operators in the control room. This individual will have a method to re-close the opening prior to reaching any of the conditions above due to loss of RHR cooling. By taking action to re-close the opening, inventory will not be lost.

McGuire Units 1 and 2165-2Rvso11 16.5.1-2 Revision 151

Inventory Control-Reduced Inventory Operation 16.5.1 BASES Continued The vent path may be satisfied by:

1. Hot leg nozzle dam not installed on the vented loop AND Removal of either of the following on the vented loop:
a. Hot leg diaphragm and manway OR
b. Cold leg diaphragm and manway (with associated coid leg nozzle dam installed*)

OR

2. Reactor vessel head is removed.
  • Installation of the associated cold leg nozzle dam avoids diversion of makeup flow (injected via a cold leg nozzle) intended for the core.

McGuire Units 1 and 216513Rvio11 16.5.1-3 Revision 151

Inventory Control-Reduced Inventory Operation 16.

5.1 REFERENCES

1. Generic Letter 88-17, Loss of Decay Heat Removal
2. NUREG 1410, Loss of Vital AC Power and Residual Heat Removal During Mid-Loop Operation at Vogtle Nuclear Station.
3. Integrated Scheduling Management Procedure 3.1, Outage Planning and Execution Responsibilities
4. McGuire Nuclear Station responses to GL 88-17, dated January 3, 1989, February 2, 1989, March 10, 1989 and February 24, 1993.
5. Nuclear Station Directive NSD-403, Shutdown Risk Management (Modes 4, 5, 6, and No-Mode) per 10 CFR 50. 65(a)(4).
6. Design Study CNDS-0242, Catawba and McGuire Nuclear Stations, Shutdown By Decay Heat Level Before Mid-Loop Operation, Safety Analysis, Nuclear Engineering, Nuclear Services.
7. Design Study MGDS-0228/CNDS-0218, McGuire/Catawba Nuclear Stations, Loss of Decay Heat Removal With Steam Generator Mitigation, Safety Analysis, Engineering Support Section, Design Engineering Department.
8. PIP M-08-05725.
9. PIP M-09-04863.
10. PIPs M-1 4-1 0887, and M-14-1 0888.

McGuire Units 1 and 216514Rvso11 16.5.1-4 Revision 151

Retrieved from "https://kanterella.com/w/index.php?title=ML15289A063&oldid=2446689"