ML21281A208

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SLC Manual, Revision to Loes and 16.7-9
ML21281A208
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 09/14/2021
From:
Duke Energy
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
JR-NUC-CN-012911
Download: ML21281A208 (13)


Text

  • lstribution:

Duke Energy Date: 9/14/2021 Document Transmittal #: JR-NUC-CN-012911

1. (CNS) U S NUC REG WASHINGTON DC DOCUMENTTRANSMITTALFORM

Purpose:

~

2. Andrews, Sherry E
3. Byers, Kristi S Released By:
4. CNS - WCC/SSA Facility: CATAWIIA N!.!CLE;AR STATION Duke E;nergi
5. CNS CIR DWGS. SSA SUBJECT 4800 Com;1mi R12111i
6. CNS COMPL FILE (ORIG)X

$1.C Mll:!!.!11 Rni1ion to !.QES 1nd 1!P-9 120,ument M1m1gement

7. CNS DOC MGMT CN04DM B.

CNS OPS SUPPORT GROUP York.SC29M5

!1.

CNS RP LIBRARY CNSl2CBMCd1,1!re-enerqy.i;;om

10. CNS RP SHIFT LAB
11. CNS RP SHIFT OFFICE
12. CONTROL ROOM SSA
13. Edmond, Russell L
14. Lowery, Tonya Sullivan
15. Mlronenko, Artur N
16. OPS TRAINING
17. Owens, Lori
18. Pursley, Sandy
19. WESTINGHOUSE ELECTRIC CO LLC Page 1 of 1 Document ID I, --1 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 17 18 19 CN - CN

  • CNS-SLC* 16.7-9
  • 005 - ISSUED FYIIE FYIIE FYIIE FYI I LP FYIIE FYIIE FYIIE FYIIE FYIIE FYIIE FYIIE FYIILP FYIIE FYIIE FYIIE FYIIE FYIIE FYIIE FYIIE CN
  • CNS-SLC*LOES
  • 101
  • ISSUED FYIIE FYIIE FYIIE FYIILP FYIIE FYIIE FYIIE FYIIE FYIIE FYIIE FYIIE FYIILP FYIIE FYIIE FYIIE FYIIE FYIIE FYIIE FYIIE CN
  • CN - SLC Letter to Manual Holders -

FYIIE FYIIE FYIIE FYIILP FYIIE FYIIE FYIIE FYIIE FYIIE FYIIE FYIIE FYIILP FYIIE FYIIE FYIIE FYIIE FYIIE FYIIE FYIIE 11

  • ISSUED emarks:

Remove and Insert Replace the following page(s) of Catawba Nuclear Station Selected Licensee Commitments (SLC) Manual with the attached revised page(s). The revised page(s) are identified by Section number and contains marginal lines Indicating the areas of change.

REMOVE THESE PAGES INSERT THESE PAGES LIST OF EFFECTIVE SECTIONS Pages 1-5 Revision 100 16.7-9, Pages 1-6 Revision 12 TAB 16.7 Pages 1-5 Revision 101 16.7-9, Pages 1-6 Revision 13 If you have any questions concerning the contents of this Catawba Nuclear Station Selected

  • ,,//:,

Licensee Commitments (SLC) Manual update, please contact Nicole Edwards (704) 591-3907.

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LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE TABLE OF CONTENTS 15 05/10/16 16.1 1

08/27/08 16.2 2

08/21/09 16.3 1

08/21/09 16.5-1 7

03/30/21 16.5-2 Deleted 16.5-3 2

09/19/19 16.5-4 0

10/09/02 16.5-5 1

01/28/10 16.5-6 1

08/21/09 16.5-7 2

02/06/15 16.5-8 Deleted 16.5-9 Deleted 03/02/21 16.5-10 Deleted 16.6-1 0

10/09/02 16.6-2 Deleted 16.6-3 1

08/21/09 16.6-4 2

11/21/19 16.6-5 3

07/07/20 16.7-1 1

08/21/09 16.7-2 4

02/03/11 16.7-3 5

11/21/19 16.7-4 2

08/21/09 16.7-5 5

04/20/21 Catawba Units 1 and 2 Page 1 Revision 101

LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE 16.7-6 3

06/10/16 16.7-7 1

08/21/09 16.7-8 2

08/21/09 16.7-9 13 09/14/21 16.7-10 9

04/23/20 16.7-11 1

08/21/09 16.7-12 1

08/21/09 16.7-13 3

06/10/16 16.7-14 1

08/21/09 16.7-15 1

08/21/09 16.7-16

---0 06/08/09 16.7-17 0

02/10/15 16.7-18 0

05/10/16 16:a-1 7

06/01/20 16.8-2 3

12/18/19 16.8-3 1

10/24/06 16.8-4 2

11/05/07 16.8-5 3

08/21/09 16.9-1 10 01/29/19 16.9-2 6

08/03/17 16.9-3 5

07/03/18 16.9-4 5

09/11/17 16.9-5 11 10/08/19 16.9-6 12 07/03/18 Catawba Units 1 and 2 Page 2 Revision 101

LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE 16.9-7 4

08/21/09 16.9-8 5

08/21/09 16.9-9 3

08/21/09 16.9-10 5

08/21/09 16.9-11 3

08/21/09 16.9-12 3

02/10/15 16.9-13 4

09/27/16 16.9-14 1

09/25/06 16.9-15 2

08/21/09 16.9-16 2

08/21/09 16.9-17 0

10/09/02 16.9-18 Deleted 16.9-19 3

02/20/12 16.9-20 0

10/09/02 16.9-21 1

10/13/16 16.9-22 1

08/21/09 16.9-23 5

08/03/17 16.9-24 2

10/24/06 16.9-25 2

08/21/09 16.9-26 1

11/15/18 16.10-1 1

08/21/09 16.10-2 1

10/24/06 16.10-3 1

08/21/09 16.10-4 0

08/04/20

- - l Catawba Units 1 and 2 Page 3 Revision 101

LIST OF EFFECTIVE SECTIONS SECTION REVISION NUMBER REVISION DATE 16.10-5 1

03/16/21 16.11-1 1

07/27/13 16.11-2 6

05/13/21 16.11-3 0

10/09/02 16.11-4 1

08/21/09 16.11-5 0

10/09/02 16.11-6 3

08/03/15 16.11-7 12 08/06/20 16.11-8 0

10/09/02 16.11-9 0

10/09/02 16.11-10 1

08/21/09 16.11-11 1

03/20/03 16.11-12 0

10/09/02 16.11-13 1

07/27/13 16.11-14 0

10/09/02 16.11-15 0

10/09/02

~6.11-16 1

10/24/11 16.11-17 0

10/09/02 16.11-18 1

08/21/09 16.11-19 0

10/09/02 16.11-20 3

11/21/19 16.11-21 0

10/09/02 16.12-1 0

10/09/02 16.13-1 1

08/03/17.

16.13-2 Deleted Catawba Units 1 and 2 Page4 Revision 101

SECTION 16.13-3 16.13-4 Catawba Units 1 and 2 LIST OF EFFECTIVE SECTIONS REVISION NUMBER Deleted 3

Page 5 REVISION DATE 04/15/20 Revision 101

16.7 INSTRUMENTATION 16.7-9 Standby Shutdown System (SSS)

COMMITMENT The SSS shall be FUNCTIONAL.

APPLICABILITY:

MODES 1, 2, and 3.

REMEDIAL ACTIONS sss 16.7-9


NOTE---------------

SLC 16.2.3 is not appUcable.

CONDITION REQUIRED ACTION COMPLETION TIME A.

SSS non-functional.

A.1 Restore SSS to 7 days FUNCTIONAL status.

B.

Total accumulative B.1 Declare the standby Immediately I

LEAKAGE from makeup pump non-unidentified LEAKAGE, functional and enter identified LEAKAGE, Condition A.

and reactor coolant pump seal LEAKAGE >

20 gpm.

C.

A required cell in a 24-C. 1 Enter Condition A.

Immediately Volt battery bank is<

1.36 volts on float charge.

D.

Required Action and D.1 Prepare and submit a 14 days associated Completion Special Report to the NRG Time of Condition A not outlining the extent of met.

repairs required, schedule for completing repairs, and basis for continued operation I

Catawba Units 1 and 2 16.7-9-1 Revision 13

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TESTING REQUIREMENTS TEST TR 16.7-9-1 Venfy that the electrolyte level of each SSS diesel starting 24-Volt battery is.:::. the low mark and ~ the high mark.

TR 16.7-9-2 Verify that the overall SSS diesel starting 24-Volt battery voltage is.:::. 24 volts on float charge TR 16.7-9-3 Verify that the requirements of SLC 16.9-21 are met and the boron concentration in the storage pool is ~ the minimum specified in the COLR.

TR 16.7-9-4 Verify the fuel level in the SSS diesel generator fuel storage tank is ~ 67 inches.

TR 16.7-9-5 Verify the SSS diesel generator starts from ambient conditions and operates for~ 30 minutes at.:::. 700 kW.

TR 16.7-9-6 Verify that the electrolyte level of each SSS 250/125-Volt battery is above the plates.

TR 16.7-9-7 Verify the total SSS 250/125-Volt battery terminal voltage is ~ 258/129 volts on float charge.

TR 16.7-9-8 Perform CHANNEL CHECK of each SSS instrumentation device.

TR 16.7-9-9 Verify the fuel oil properties of new and stored fuel oil for the SSS diesel generator are tested in accordance with, and maintained within the limits of, the Diesel Fuel Oil Testing Program.

TR 16.7-9-10 Verify that the individual battery cell voltage of the required cells in the SSS diesel starting 24-Volt battery is

~ 1.36 volts on float charge.

Catawba Units 1 and 2 16.7-9-2 sss 16.7-9 FREQUENCY 7 days 7 days 7 days 31 days 31 days 31 days 31 days 31 days In accordance with the Diesel Fuel Oil Testing Program 92 days (continued)

Revision 13

T ESTING REQUIREMENTS (continued)

TEST TR 16.7-9-11 Verify that the Standby Makeup Pump's developed head at the test flow point is~ the required developed head, in accordance with the lnservice Testing Program.

TR 16.7-9-12 Verify that the specific gravity of the SSS 250/125-Volt battery is appropriate for continued service of the battery.

TR 16.7-9-13 Subject the SSS diesel generator to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for the class of service.

TR 16.7-9-14 Verify that the SSS diesel starting 24-Volt batteries, cell plates, and battery racks show no visual indication of physical damage or abnormal deterioration.

TR 16.7-9-15 Verify that the SSS diesel starting 24-Volt battery-to-battery and terminal connections are clean, tight, and free of corrosion.

TR 16.7-9-16 Verify that the SSS 250/125-Volt batteries, cell plates, and battery racks show no visual indications of physical damage or abnormal deterioration~

TR 16.7-9-17 Verify that the SSS 250/125-Volt battery-to-battery and terminal connections are clean, tight, free of corrosion, and coated with anti-corrosion material.

TR 16.7-9-18 Verify that the steam turbine driven auxiliary feedwater pump and controls from the Standby Shutdown Facility function as designed from the SSS.

TR 16.7-9-19 Perform CHANNEL CALIBRATION of each SSS instrumentation device.

Catawba Units 1 and 2 16.7-9-3 sss 16.7-9 FREQUENCY 92 days 92 days 18 months 18 months 18 months 18 months 18 months 18 months 18 months (continued)

Revision 13 I

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sss 16.7-9 TESTING REQUIREMENTS (continued)

TEST FREQUENCY TR 16. 7-9-20 Verify proper installation of pressurizer insulation.

18 months TR 16.7-9-21 Venfy pressurizer heaters powered from the SSS have a 18 months capacity of~ 63. 5 kW measured at motor control center SMXG.

TR 16. 7-9-22 Verify flowpath from the reactor vessel head through the 18 months BASES valves powered from the SSS is unobstructed.

The SSS is designed to mitigate the consequences of certain postulated fire, security, and station blackout incidents by providing capability to maintain MODE 3 conditions and by controlling and monitoring vital systems from locations external to the main control room. This capability is consistent with the requirements of 10 CFR Part 50.48(c).

When the SSS is under Condition A and it is anticipated that Condition D will be utilized, establish the bases for continued operation (including any supporting actions) prior to entering Condition D. Risks associated with the continued operation under Condition D are evaluated and managed through existing processes and procedures These risk contributors, risk insights, risk-infonned information, and/or risk mitigation actions assessed and managed during periods when Condition D is applied, are to be included in the 14-day special report.

The TESTING REQUIREMENTS ensure that the SSS systems and components are capable of perfonning their intended functions The required level in the SSS diesel generator fuel storage tank ensures sufficient fuel for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> uninterrupted operation. It is assumed that, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, either offsite power can be restored or additional fuel can be added to the storage tank.

Although the standby makeup pump is not nuclear safety related and was not designed according to ASME Code requirements, it is tested quarterly to ensure its FUNCTIONALITY. The TESTING REQUIREMENT concerning the standby makeup pump water supply ensures that an adequate water volume is available to supply the pump continuously for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Total accumulative LEAKAGE is calculated in the NC System Leakage Calculation procedure as identified + unidentified + seal leakoff (References 2 and 3). The REMEDIAL ACTION limit of 20 gpm total accumulative LEAKAGE provides additional margin to allow for Catawba Units 1 and 2 16.7-9-4 Revision 13

BASES (continued) sss 16.7-9 instrument inaccuracy, and for the predicted increase in seal leakoff rate due to heatup of the reactor coolant pump seal injection water supply

'temperature following the SSS event (due to spent fuel pool heatup).

Following the increase in seal injection temperature, the standby makeup pump flow of 26 gpm is sufficient to provide in excess of this total accumulative LEAKAGE, thereby assuring that reactor coolant system inventory is maintained at MODE 3 conditions. The supporting evaluation is provided in CNC-1223.04-00-0072 (Ref. 4).

A visual inspection of the diesel starting 24-volt batteries, cell plates, and battery racks provides an indication of physical damage or abnormal deterioration that could potentially degrade battery performance. Since the battery cell jars are not transparent, a direct visual inspection of the cell plates cannot be performed. Instead, the cell plates are inspected for physical damage and abnormal deterioration by: 1) visually inspecting the jar sides of each cell for excessive bowing and/or deformation, and 2) visually inspecting the electrolyte of each cell for abnormal appearance.

Verifying individual cell voltage while on float charge for the SSS diesel starting 24-Volt batteries ensures that each cell is capable of supporting its intended function. Float charge is the condition in which the charger is supplying the continuous charge requirecfto overcome th-eintern~aI-rosses- - -

of a battery (or battery cell) and maintaJn the battery (or battery cell) in a fully charged state. The battery cell voltage limit of 1.36 volts is consistent with the nominal design voltage of the battery and is based on the manufacturer's recommended minimum float charge voltage for a fully charged cell with adequate capacity. The 24-Volt starting battery is designed with two battery banks, each battery bank contains 20 individual battery cells. The 24-Volt starting battery has sufficient capacity margin to maintain SSS diesel starting functionality with one cell in each battery bank to be fully degraded with a voltage< 1.36 volts. The 24-Volt starting battery is required to have 19 individual battery cells per battery bank to maintain SSS diesel starting functionality with sufficient capacity margin.

The battery sizing calculation accounts for one degraded cell in each battery bank by assuming the degraded cells undergo a worst case polarity reversal during SSS diesel starting. The supporting evaluation is provided in CNC-1381. 06-00-0056 (Ref.12).

Verification of proper installation of pressurizer insulation ensures that pressurizer heat losses during an SSS event do not exceed the capacity of the pressurizer heaters powered from the SSS.

Testing of the pressurizer heater capacity ensures the full capacity of the heaters is available to maintain a steam bubble in the pressurizer during an SSS event. The acceptance criterion includes an allowance for the voltage drop in the power cables between the SSS and the pressurizer and measurement uncertainty.

Catawba Units 1 and 2 16 7-9-5 Revision 13 I

sss 16.7-9 BASES (continued)

REFERENCES Testing of the flowpath from the reactor vessel head to the pressurizer relief tank ensures sufficient flow capacity for reactor coolant inventory control during an SSS event.

1.

Letter from NRC to Gary R Peterson, Duke, Issuance of Improved Technical Specifications Amendments for Catawba, September 30, 1998.

2.

PT/1(2)/N4150/001D, NC System Leakage Calculation.

3.

PT/1(2)/N4150/001I, Manual NC Leakage Calculation.

4.

CNC-1223.04-00-0072, Reactor Coolant Pumps No. 1 Seal Leakoff Annunciator Alarm Setpoint for Unit 1 and Unit 2.

5.

CNS-1560.SS-00-0001, Design Basis Specification for the Standby Shutdown Facility.

6.

Catawba Technical Specification Amendments 206/200, July 10, 2003.

7.

Catawba UFSAR, Section 18.2.4.

8.

Catawba License Renewal Commitments, CNS-1274.00 0016, Section 4.5.

9.

CNC-1223.03-00-0033, Determination of Pressurizer Heater Capacity Powered from the SSF Diesel.

10.

Catawba Nuclear Station 10 CFR 50.48(c) Fire Protection Safety Evaluation (SE).

11 1 0 CFR 50.48(c), Fire Protection.

12.

CNC-1381.06-00-0056, SSF Diesel Generator Battery Sizing Calculation.

Catawba Units 1 and 2 16.7-9-6 Revision 13