ML100640136

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Selected Licensee Commitments Manual Update
ML100640136
Person / Time
Site: Mcguire, McGuire  Duke Energy icon.png
Issue date: 02/25/2010
From: Beaver B
Duke Energy Corp
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
DUK100560044
Download: ML100640136 (29)
v • d • e


Text

  • 'Ii

- 1oIrmal DISPOSITIO N OF THE ORIGINAL DOCUMENT WILL BE TO THE TRANS MITTAL SIGNATURE UNLESS RECIPIENT IS Date: 02125110 PRIORITY OTHERWISEEIDENTIFIED BELOW Document Transmittal #: DUK100560044 1' 02546 WC LIBRARY - MG01WC

2) 03044 MCG I C CNTRL MISC,.MAN MG05DM ;Duke Energy QA CONDITION [: Yes
  • No
3) -03379 D E C LDWELL MG01MM OTHER ACKNOWLEDGEMENT REQUIRED N Yes
4) 03447 HARRf' J SLOAN MG01RP DOCU MENT TRANSMITTAl FORM IF QA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASE
5) 03614 MCG , PS PROCEDURE GP MG01OP ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO:

REFERENCE

6) 03744 OPS Ti*NG MGR. MG03OT
7) 03759 U S NUC REG WASHINGTON, DC MCGUIRE NUCLEAR STATION Duke Energy
8) 04809 MCG PLIANT ENG. LIBR. MG05SE McGuire
9) 05162 MCG SHIFT WORK MGRS MG01OP DCRM MGO2DM SELECTED LICENSEE coMMITMEI ITS
10) 09460 W C SPENCER MG01RP 13225 Hagers Ferry Road
11) 09665 JOHNi FSTANG, USNRC MANUAL (SLC) Huntersville, N.C. 28078 RECORD RETENTION # 581188 Rec'd By Page 2 of 2 Date I~~ I I~ ~ r r t DOCUMENT KIO QA COND REV #/DATE DISTR CODE 1 2 3 4 5 6 7 8 9 10 11 12 113 14 115 TOTAL II SLC MEMORAI DUM NA . 02/10/10 MADM-03A V1 x V1 V1 V8 V2 V1 V1 V1 36 SLC - LIST OF EFFECTIVE PAGES NA 097 09/22/09 SLC 16.9.7 NA 113 10/12/09 sLC 16.11.1 I NA 112 02/04/10 SLC 16.11.6 NA 112 02/04/10 II REMARKS: PLEASE UPDATE ACCORDINGLY B H HAMILTON VICE PRESIDENT iREPRO: ONE SIDED COPIES THREE HOLE PUNCH MCGUIRE NUCLEAR STATION BY:

B C BEAVER MCO1RC BCB/TLC

- DISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TO NORY ormal THE TRANSM ITTAL SIGNATURE UNLESS RECIPIENT IS Date: 02125/10 PRIORITY 'OTHERWISE IIDENTIFIED BELOW Document Transmittal #: DUKI00560044

1) 00003 NRI&IAMGR EC050
2) 00070 VICKIE BREWER - MG03OT Duke Energy QA CONDITION [] Yes
  • No
3) 00200 M E CARROLL EC08H
4) 00297 LUIS AEVES, DRPIRPBA-ATLANTA DOCUMENT TRANSMITTAL FORM OTHER ACKNOWLEDGEMENT REQUIRED
  • Yes IF QA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASE
5) 00422 MCG BONNIE C BEAVER - MG01RC ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO:

REFERENCE

6) 00485 OPS TEST GROUP - MG01OP
7) 00692 MCG OPS STAFF MGR MG01OP MCGUIRE NUCLEAR STATION Duke Energy
8) 00707 MCG SERV BLDG SAT AREA MG01 S1 McGuire
9) 00841 OPS HUMAN PERFORMANCE - MG01OP DCRM MGO2DM SELECTED LICENSEE COMMITMENTS
10) 01202 KLCRANE - MGO1RC 13225 Hagers Ferry Road
11) 01492 BLUE ,B'OTLIBRARY MG01MOD MANUAL (SLC) Huntersville, N.C. 28078
12) 01503 VICKIE LMC GINNIS- MG03OT
13) 01623 G LMONTGOMERY

'Ii MG01WC RECORD RETENTION # 581188

14) 02467 ELECT. LICENSING LIBRARY EC050
15) 02532 MCG NRC INSP MG-ADMIN MAIL RM Recd By Page 1 of 2 Date DOCUMENTINO QACOND REV #/DATE DISTR CODE 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 TOTAL SLC MEMORAIVIDUM NA . 02/10/10 MADM-03A V1 V1 V1 V1 V3 V1 V1 Vi V1 V1 V1 V1 V1 V1 V1 36 SLC - LIST OF, EFFECTIVE PAGES NA 097 09/22/09 SLC 16.9.7 NA 113 10/12/09 SLC 16.11.1 NA 112 02/04/10 SLC 16.11.6 i NA 112 02/04/10

[I REMARKS: PLEASE UPDATE ACCORDINGLY B H HAMILTON VICE PRESIDENT REPRO: ONE SIDED COPIES MCGUIRE NUCLEAR STATION j! THREE HOLE PUNCH BY:

B C BEAVER MCO1RC BCB/TLC I

February 10, 2010 MEMORANDUM To: All McGuire Nuclear Station Selected Licensee Commitments (SLC) Manual Holders

Subject:

McGuire SLC Manual Update Please revise your copy of the manual as follows:

REMOVE INSERT List: of Effective Sections (Rev 96) List of Effective Sections (Rev 97)

SLC 16.9.7 Entire Section (Rev 105) SLC 16.9.16 Entire Section (Rev 113)

., SLC 16.11.1 Entire Section (Rev 9) SLC 16.11.1 Entire Section (Rev 112)

SLC 16.11.6 Entire Section (Rev 59) SLC 16.11.6 Entire Section (Rev 112)

Revisions may-skip numbers due to Regulatory Compliance Filing System.

Please call me if you have questions.

Bonnie Beaver Regulatory Compliance

SELECTED LICENSEE COMMITMENTS (SLC)

LOES SLCs ARE REVISED PER SECTION SECTION T REVISION NUMBER DATE 16.1 REVISION 32 12/2/02 16.2 REVISION 90 3/13/07 16.3 REVISION 48 7/31/03 16.4 Not Issued 16.5.1 REVISION 82 6/12/06 16.5.2 REVISION 0 12/14/99 16.5.3 REVISION 0 12/14/99 16.5.4 REVISION 55 3/23/04 16.5.5 REVISION 0 12/14/99 16.5.6 REVISION 0 12/14/99 16.5.7 REVISION 53 1/13/04 16.5.8 REVISION 0 12/14/99 16.5.9 REVISION 108 06/10/09 16.5.10 REVISION 38 4/9/03 16.6.1 REVISION 0 12/14/99 16.6.2 DELETED 6/11/03 16.6.3 REVISION 61 04/07/05 16.6.4 REVISION 27 06/12/02 16.7.1 REVISION 0 12/14/99 16.7.2 REVISION 80 10/1/05 16.7.3 REVISION 0 12/14/99 16.7.4 REVISION 1 4/11/00 16.7.5 REVISION 0 12/14/99 16.7.6 REVISION 103 12/03/08 16.7.7 REVISION 0 12/14/99 16.7.8 REVISION 77 10/12/05 16.7.9 REVISION 97 10/06/08 16.7.10 REVISION 0 12/14/99 16.7.11 REVISION 71 05/25/05 16.8.1 REVISION 98 11/1/07 16.8.2 REVISION 0 12/14/99 16.8.3 REVISION 65 12/21/04 16.9.1 REVISION 53 1/13/04 16.9.2 REVISION 81 6/15/06 16.9.3 REVISION 106 05/26/09 16.9.4 REVISION 83 7/12/06 16.9.5 REVISION 81 6/15/06 16.9.6 REVISION 107 5/18/09 16.9.7 REVISION 113 10/12/09 16.9.8 REVISION 96 9/10/07 16.9.9 REVISION 101 4/02/08 16.9.10 REVISION 13 2/26/01 16.9.11 REVISION 22 2/25/02 16.9.12 REVISION 101 4/02/08 16.9.13 Not Used - Rev 13 2/26/01 McGuire Units 1 and 2 I Revision 97

SELECTED LICENSEE COMMITMENTS (SLC)

LOES -

SLCs ARE REVISED PER SECTION SECTION REVISION NUMBER DATE 16.9.14 REVISION 22 2/25/02 16.9.15 REVISION 100 3/11/08 16.9.16 REVISION 111 09/09/09 16.9.17 REVISION 86 1/17/07 16.9.18 REVISION 0 12/14/99 16.9.19 REVISION 102 9/3/08 16.9.20 REVISION 8 11/30/00 16.9.21 REVISION 0 12/14/99 16.9.22 REVISION 109 8/13/09 16.9.23 REVISION 88 1/17/07 16.9.24 Not Used - Rev 74 6/20/05 16.9.25 REVISION 87 1/17/07 16.10.1 REVISION 56 4/6/04 16.11.1 REVISION 112 2/4/10 16.11.2 REVISION 84 7/19/06 16.11.3 REVISION 0 12/14/99 16.11.4 REVISION 0 12/14/99 16.11.5 REVISION 0 12/14/99 16.1.1.6 REVISION 112 2/4/10 16.11.7 REVISION 84 7/19/06 16.11.8 REVISION 0 12/14/99 16.11.9 REVISION 0 12/14/99 16.11.10 REVISION 0 12/14/99 16.11.11 REVISION 41 8/21/03 16.11.12 REVISION 67 2/28/05 16.11.13 REVISION 91 3/22/07 16.11.14 REVISION 21 1/17/02 16.11.15 REVISION 21 1/17/02 16.11.16 REVISION 1 4/11/00 16.11.17 REVISION 110 8/20/09 16.11.18 REVISION 0 12/14/99 16.11.19 REVISION 0 12/14/99 16.11.20 REVISION 0 12/14/99 16.12.1 REVISION 0 12/14/99 16.12.2 REVISION 0 12/14/99 16.13.1 REVISION 51 10/1/03 16.13.2 Not Used - Rev 75 8/05 16.13.3 Not Used - Rev 75 8/05 16.13.4 REVISION 58 5/11/04 16.14.1 REVISION 0 12/14/99 16.14.2 REVISION 104 3/18/09 McGuire Units 1 and 2 Revision 97

Standby Shutdown System 16.9.7 16.9 AUXILIARY SYSTEMS - FIRE PROTECTION SYSTEMS 16.9.7 Standby Shutdown System COMMITMENT The Standby Shutdown System (SSS) shall be operable.

APPLICABILITY MODES 1, 2, and 3.

REMEDIAL ACTIONS

IKItl -r I

Krrr

-I------------------------------------------------------

1. The SRO should ensure that security is notified 10 minutes prior to declaring the SSS inoperable. Immediately upon discovery of the SSS inoperability, Security must be notified to implement compensatory measures within 10 minutes of the discovery.
2. If inoperable SSS component is located inside containment, repairs shall be made at the first outage which permits containment access.

CONDITION REQUIRED ACTION COMPLETION TIME

- NOTE ---------- A.1 Verify the OPERABILITY of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Not applicable to the SSS fire detection and Diesel Generator or 24 V suppression systems in the Battery Bank and Charger. associated areas identified in Table16.9.7-1.

A. One or more required AND SSS components identified in Table A.2 Restore the component to 7 days 16.9.7-1 inoperable. OPERABLE status.

B. SSS Diesel Generator or B.1 Verify the OPERABILITY of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 24 V Battery Bank and fire detection and Charger inoperable. suppression systems in the associated areas identified in Table16.9.7-1.

AND (continued)

McGuire Units 1 and 2 16.9.7-1 Revision 113

Standby Shutdown System 16.9.7 REMEDIAL ACTIONS (continued CONDITION REQUIRED ACTION COMPLETION TIME B. (continued). B.2 Verify offsite power and 1hour one emergency diesel generator OPERABLE.

AND B.3 Restore the component to 7days OPERABLE status.

C. Total Unidentified C.1 Declare the Standby Immediately LEAKAGE, Identified Makeup Pump inoperable.

LEAKAGE, and reactor coolant pump seal AND leakoff > 20 gpm.

C.2 Enter Condition A.

OR Total reactor coolant pump seal leakoff > 16.3 gpm.

D. Lake Norman level D.1 Verify the "C" Fire 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> below 746 feet. Suppression Pump is OPERABLE (Unit 1 only).

E. Required Action A.2 and E.1 Prepare and submit a 30 days its associated Special Report to the NRC Completion Time not outlining the cause of the met. inoperability, corrective actions taken, and plans for restoring the SSS to OPERABLE status.

F. Required Action B.3 and F.1 Prepare and submit a 14 days its associated Special Report to the NRC Completion Time not outlining the extent of met. repairs required, schedule for completing repairs, and, basis for continued operation.

McGuire Units 1 and 2 16.9.7-2 . Revision 113

Standby Shutdown System 16.9.7 TESTING REQUIREMENTS TEST FREQUENCY TR 16.9.7.1 Verify total Identified LEAKAGE, Unidentified LEAKAGE, 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and reactor coolant pump seal leakoff are <.20 gpm.

AND Verify total reactor coolant pump seal leakoff < 16.3 gpm.

TR 16.9.7.2 Verify the requirements for spent fuel water level in 7 days Surveillance Requirement 3.7.13.1 are met and the boron concentration in the spent fuel storage pool is within the limits specified in the COLR.

OR Verify the refueling water storage tank is capable of being alicined to the SSS standby makeup pump.

TR 16.9.7.3 Verify fuel oil level in the SSS diesel generator fuel 31 days storage tank is > 4.0 ft.

TR 16.9.7.4 Verify the SSS diesel generator starts from ambient 31 days conditions and operates for > 30 minutes at > 700 kW.

TR 16.9.7.5 Verify fuel oil properties of new and stored fuel oil for the In accordance with SSS diesel generator are tested in accordance with, and the Diesel Fuel Oil maintained within the limits of, the Diesel Fuel Oil Testing Testing Program Program.

TR 16.9.7.6 Verify the SSS diesel generator 24 V battery voltage is > 31 days 24 volts.

TR 16.9.7.7 Perform a CHANNEL CHECK of the SSS Instrumentation 31 days as required by Table 16.9.7-2.

TR 16.9.7.8 Verify the electrolyte level of each SSS 250/125 V battery 31 days bank is above the plates.

(continued)

McGuire Units 1 and 2 16.9.7-3 Revision 113

Standby Shutdown System 16.9.7 TESTING REQUIREMENTS (continued)

TEST FREQUENCY TR 16.9.7.9 Verify the total battery terminal voltage of each SSS 31 days 250/125 V battery bank is > 258/129 V on float charge.

TR 16.9.7.10 Verify the average specific gravity of each SSS 250/125 92 days V battery bank is > 1.200.

TR 16.9.7.11 Verify the standby makeup pump's developed head and 92 days capacity is greater than or equal to that required by the Inservice Testing Supplemental Program.

TR 16.9.7.12 Verify the SSS diesel generator 24 V batteries and 18 months battery racks show no visual indication of physical damage or abnormal deterioration.

-TR -16.9:7.13 Verify SSS-d ieselge-nat-T24 V-b-attery -to battery-rd .. 8 months terminal connections are clean, tight, and free of l.,1.JI I 'J*IUJI I.*

TR 16.9.7.14 Perform a CHANNEL CALIBRATION of the SSS 18 months Instrumentation as required by Table 16.9.7-2.

TR 16.9.7.15 Perform inspection of SSS diesel generator in 18 months accordance with procedures prepared in conjunction with manufacturer's recommendations for class of service.

TR 16.9.7.16 Verify the SSS 250/125 V batteries, cell plates, and 18 months battery racks show no visual indication of physical damage or abnormal deterioration.

TR 16.9.7.17 Verify the SSS 250/125 V battery to battery and terminal 18 months connections are clean, tight, free of corrosion, and coated with anti-corrosion material.

TR 16.9.7.18 Verify the "C" solenoid to valve SA48ABC can be 18 months deenergized to provide steam supply to the turbine driven auxiliary feedwater pump.

TR 16.9.7.19 Verify the CA Storage Tank level is > 20 feet. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TR 16.9.7.20 Verify Lake Norman level is > 746 feet 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> McGuire Units 1 and 2 16.9.7-4 Revision 113

OLC311ULJY QIIULUUVVII OybMill 16.9.7 0 I TABLE @.7-1 STAN[ )BY SHUTDOWN S) STEM FIRE DETECTION & S JPPRESSION SYST --MS VERIFICATION(1 )

INOPERABLE SSS COMPONENT _ FIRfE DETECTION & St .PPRESSION SYSTEMS LOCATION EL 716 EL 733 EL 7ý 0 Control Batter Cable Turbine Driven Motor Driven Containment EE-KK EE-KK EE.I4K Room Roor_ Rooms AFW Pump AFW Pump SSS Diesel Generator(3) X X X X X X X X Note 2 SSS DG Starting 24 V Battery X X X X X X X X Note2 Bank and Charger(3)

Standby Makeup Pump and X X X Water Supply SSS 250/125V Battery and X X X Note 2 Charger(3 Turbine Driven AFW Pump and X Water Supplies(4 _

Turbine Driven AFW Pump X Solenoid "C" Groundwater Drainage Sump X Pump A, Sump A AND Groundwater Drainage Sump Pump A, Sump B Fire Suppression Pump "C"(see X Condition D).

INSTRUMENTATION:

1. RCS Pressure X X X Note 2
2. Pressurizer Level _ _ _X X X Note 2
3. SG Level _ - , X _X X Note 2
4. Incore Temperature _ X X X Note 2
5. NC Wide Range Cold Leg X X X Note 2 Temperature _ _

NOTES:

1. If fire detection and/or suppression systems are inopernible, then the ACTIOI I statement(s) of the applicable fire detection and/or suppression SLC shall be complied with.
2. Monitor containment air temperature at least once per 1iour at the locations c jecified in Technical Specification Surveillance Requirement 3.6.5.1 or 3.6.5.2, in lieu-of verification of operability of systems inside contai iment.
3. With this component inoperable, then denoted areas o6 both units are affectE
4. Water supplies include the Auxiliary Feedwater Stora ( Tank (CAST) and C )ndenser Circulating Water (RC) System via valves CA-1 61C and 162C. Continuous vents at 1/2RN-1 065 and 1RN- 1066 support OPERA 3ILITY of the RC source for Unit I only.

McGuire Units 1 and 2 16.9.7-5 Revision 113

Standby Shutdown System 16.9.7 TABLE 16.9.7-2 STANDBY SHUTDOWN SYSTEM INSTRUMENTATION TESTING REQUIREMENTS REQUIRED TESTING READOUT INSTRLJMENT CHANNELS REQUIREMENTS LOCATION

1. Reactor Coolant Pressure 1 TR 16.9.7.7 SSF Control TR 16.9.7.14 Panel
2. Pressurizer Leve 1 1 TR 16.9.7.7 SSF Control TR 16.9.7.14 Panel
3. Steam Generato r Level 1 per SG TR 16.9.7.7 SSF Control (Wide Range) TR 16.9.7.14 Panel
4. Incore Temperat ure 1 TR 16.9.7.7 SSF Control TR 16.9.7..14 Panel
5. StandbyyMaketup Pump Flow 1 i16.9. 7.14 SSFi Control Panel O 6. NC Wide Range Cold Leg 2 TR 16.9.7.7 TR 16.9.7.14 SSF Control Temperature Panel TR 16.9.7.14 Panel McGuire Units 1 and 2 16.9.7-6 Revision 113

Standby Shutdown System 16.9.7

. BASES The Standby Shutdown System (SSS) is designed to mitigate the consequences of certain postulated fire incidents, sabotage, or station blackout events by providing capability to maintain HOT STANDBY conditions and by controlling and monitoring vital, systems from locations external to the main control room. The facility is credited with the ability to cope with a station black out (SBO) event of 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> duration. Thiscapability is consistent with the requirements of 10 CFR Part 50, Appendix R and 10 CFR 50.63.

By design, the SSS is intended to respond to those low-probability events which render both the control room and automatic safety systems inoperable. Because of the low probability of occurrence of these events, the remedial actions rely on compensatory action, timely repair or return to operability and, if necessary, a justification for continued operation.

Because the SSS performs a redundant fire protection function, compensatory action during periods when the SSS is inoperable relies largely on assurance of the operability of fire detection and suppression systems. Table 16.9.7-1 establishes requirements for operability of fire detection and suppression systems.

Both A&D NC Cold Leg Wide Range Temperatures are required for SSS operability. This conclusion is based on NRC Correspondence during issuance of the original operating 11cense.

The Source Range Wide Range Neutron Flux Instrumentation was installed at the SSS Control Panel as part of NRC review of this system in the early 1980s. The indication is not required for SSS operability, based on the NRCs response to Duke dated July 12, 1983.

Controls and power to the pressurizer heater banks are included for SSF events; however, they are not required for SSS operability. NRC Generic Letter 86-10 provides that conclusion.

The Testing Requirements ensure that the SSS systems and components are capable of performing their intended functions. The testing requirements were based largely on SSS Technical Specifications for the Catawba Nuclear Station, which was approved prior to the issuance of the fuel load license for Unit 1 of that plant. Also considered in the formulation of the testing requirements were existing McGuire Technical Specifications, such as those for the 1E Diesel Generators, Refueling Water Storage Tank, Fire Protection & Detection Systems, and other Tech Specs which are related to the safe operation and/or shutdown of the plant.

The required level in the SSS diesel generator fuel storage tank ensures sufficient fuel for 3 Y2 days of uninterrupted operation. Per Appendix R requirements, the unit must be in cold shutdown within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of going to the SSF. The 3 / day supply of fuel oil assures this capability.

Testing has demonstrated the ability of plant operations to start the SSF diesel within 10 minutes of the recognition of an SBO event, thus satisfying the intent of NUMARC 87-00 guidance. The SSF diesel generator has sufficient capacity and capability to operate equipment necessary to achieve and maintain safe shutdown conditions for a 4-hour SBO event.

McGuire Units 1 and 2 16.9.7-7 Revision 113

Standby Shutdown System 16.9.7

. BASES (continued)

Fuel oil for the SSS diesel generator is tested and maintained in accordance with the same Diesel Fuel Oil Testing Program used for the 4kV emergency diesel generators (see Technical Specification 5.5.13, Surveillance Requirement 3.8.3.2 and associated 'Bases).

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 OPERABILITY.

The Standby Makeup Pump (SMP) functions as part of the SSF to provide makeup capacity to the reactor coolant system and cooling flow to the reactor coolant pump (RCP) seals.

The RCP seal leak-off flow is temperature dependent (i.e., the higher the temperature the higher the leak-off flow). During normal operation the RCP seals are supplied from the Centrifugal Charging Pump (CCP) drawing from the Volume Control Tank (VCT). During the SSF event, the SMP draws from the Spent Fuel Pool (SFP). During the SSF event there is no SFP cooling, so water injected into the RCP seals will have a higher temperature than during normal operation. The SMP is capable of providing a makeup capacity of 26 gpm.

The revised SLC limit of 20 gpm total accumulative leakage is based on a calculation that was performed by Westinghouse, indicating increased RCP seal leak-off at higher seal water temperatures, to relate the SSF event leakage of 26 gpm at elevated RCP seal temperatures. This more conservative limit will ensure that the SMP will be capable of providing makeup and seal cooling flow equal to or greater than total leakage during the SSF event, increased rMA seal leak-off flow due to heat-up of-tne-SFP, and still provide a margin of safety. As a conservative measure, during normal power operation the total accumulative system leakage (unidentified + identified + RCP seal leak-off flows) shall be limited to 20 gpm. The Testing Requirement concerning the SMP 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 />.

The additional requirement that total RCP seal leak-off flow be < 16.3 gpm resulted from a historical review of NRC correspondence that specified the SMP also provide for reactor coolant system makeup and boration in addition to RCCP seal leakage requirements (Ref.

17). Calculations show that this upper limit for RCP seal leak-off provides sufficient margin to maintain the required unit conditions for a bounding SSS event.

The Groundwater Drainage Sump Pump A, in the A (Unit 1) and B (Unit 2) sumps, can be controlled and powered from the SSF. These Sump Pumps remove accumulation of groundwater, Turbine driven AFW Pump drains, and other miscellaneous sources. For the SSS to be OPERABLE, a minimum of one of these pumps must be OPERABLE. Credit is taken for the groundwater underdrain system to transport water from one sump to the other.

The turbine driven AFW pump can be controlled from the SSF and is utilized during an SSS event to maintain adequate secondary side heat removal. For the SSS to be OPERABLE, the turbine driven AFW pump must be OPERABLE. The turbine driven AFW pump water supply for the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> SBO event is provided by the CA Storage Tank (CAST). The water supply for the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> fire event is initially provided by the CAST then later by manual alignment to the RC system via valves CA-161C and CA-162C. These valves are maintained closed and de-energized to prevent spurious actuation and air entrainment (Ref.

22). Adequate CAST inventory of 200,000 gallons (20 feet of level) is ensured by TR

. 16.9.7.19. For a fire event, an initial CAST inventory is needed to allow time to perform the manual alignment from the CAST to the RC system. For Unit 1 only, in the remote chance that the level of Lake Norman drops below 746 feet, air entrainment from the RC system cannot be prevented. In this case, adequate water supplies for a fire event are ensured by McGuire Units 1 and 2 16.9.7-8 Revision 113

Standby Shutdown System 16.9.7

. BASES (continued) making up to the Unit 1 CAST from the Fire Suppression system using the "C" Fire Suppression pump.

The SSF is provided with its own 250/125 VDC power system which is independent from the normal 125 VDC and 120 VAC vital I&C power systems. The SSF batteries are charged by the SSF diesel generator and are available to power the SSF instruments and controls necessary to achieve and maintain hot standby conditions from the SSF control room following a station black out (SBO) event.

While the SSS 24 VDC battery charger is isolated for battery surveillance testing, the SSS Diesel Generator remains operable as long as the battery voltage is > 24 volts.

The SSS 125V batteries and battery chargers consist of three pairs SDSP1, SDSP2 and SDSS. Each pair consists of a battery and associated battery charger. Pair SDSS can be used to substitute for either pair SDSP1 or SDSP2. Only two of these pairs are required operable since pair SDSS is spare.

This selected licensee commitment is part of the McGuire Fire Protection Program and therefore subject to the provisions of McGuire Facility Operating License Conditions C.4

-(U nif1-)a ndC T.- (U nit-2 ).-..... ... - .. . ... - :.... ...- . - . --

REFERENCES

1. McGuire Nuclear Station UFSAR, Chapter 9.5.1
2. McGuire Nuclear Station SER Supplement 2, Chapter 9.5.1_and Appendix D
3. McGuire Nuclear Station SER Supplement 5, Chapter 9.5.1 and Appendix B
4. McGuire Nuclear Station SER Supplement 6, Chapter 9.5.1 and Appendix C
5. McGuire Fire Protection Review, as revised
6. McGuire Fire Protection Safe Shutdown Review
7. IEEE 308-1974, Class 1E Power Systems
8. IEEE 450-1975, Maintenance Testing & Replacement of Large Lead Storage Batteries
9. OP/O/B/6350/04, Standby Shutdown Facility Diesel Operation
10. McGuire Nuclear Station Facility Operating Licenses, Unit 1 License Condition C.(4) and Unit 2 License Condition C.(7)
11. PIP 0-M-99-03926

. 12. PIP-M-01-3466

13. 10 CFR 50.63, Loss of All Alternating Current McGuire Units 1 and 2 16.9.7-9 Revision 113

Standby Shutdown System 16.9.7

. 14. Letter from H.B. Tucker to NRC, dated April 4, 1,990, Requirements for Station Blackout.

15. Letter from H.B. Tucker to NRC, dated April 17, 1989, Requirements for Station Blackout.
16. McGuire Nuclear Station, Units 1 and 2, Safety Evaluation for Station Blackout (10CFR50.63), Dated February 19, 1992.
17. SAIC-91/1265, "Technical Evaluation Report, McGuire Nuclear Station, Station Blackout Evaluation," Dated December 10, 1991.
18. McGuire Nuclear Station UFSAR, Section 18.2.4, Chemistry Control Program.,
19. MCS-1465.00-00-0019, "Plant Design Basis Specification For Station Blackout Rule,"

Rev. 3.

20. McGuire License Renewal Commitments MCS-1274.00-00-0016, Section 4.6, Chemistry Control Program.
21. PIP M-04-3317.
22. MCC-1223.42-00-0055, "Design Considerations and Bases for 1/2CA-161C and 1/2CA-162C Automatic Open Deletion Modifications MD101869 and MD201870."

McGuire Units 1 and 2 16.9.J-10 Revision 113

Liquid Effluents - Concentration 16.1.1.1 16.11 RADIOLOGICAL EFFLUENT CONTROLS 16.11.1 Liquid Effluents - Concentration COMMITMENT The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 16.11.1-1) shall be limited:

a. For radionuclides other than dissolved or entrained noble gases, 10 times the effluent concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2, and
b. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 104 microCurie/ml total activity.

APPLICABILITY At all times.

REMEDIAL ACTIONS CONDITION .. ... REQUIRED ACTION .. COMPLETION TIME A. Concentration of A.1 Restore the concentration Immediately radioactive material to within limits.

releasedJn liquid effluents to UNRESTRICTED AREAS not within limits.

TESTING REQUIREMENTS TEST FREQUENCY TR 16.11.1.1 ------------------ NOTE -----------------

The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits.

Sample and analyze radioactive liquid wastes according According to to Table 16.11.1-1. Table 16.11.1-1 McGuire Units 1 and 2 16.11.1-1 Revision 112

Liquid Effluents - Concentration 16.11.1 TABLE 16.11.1-1 (Page 1 of 3)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID RELEASE SAMPLING MINIMUM TYPE OF LOWER LIMIT TYPE FREQUENCY ANALYSIS ACTIVITY OF DETECTION FREQUENCY ANALYSIS (LLD) microCi/ml (1)

1. Batch Waste P P Principal Each Batch Each Batch Gamma 5x1 0-7 Release Tanks (WMT and Emitters(6)

RMT)(4) 1-131, lxi 0-6 P M Dissolved and One Batch/M Entrained lxi 0. 5 Gases (Gamma emitters )(7) p M H-3 1 X10-5

--E-5c-fB-aFh-Gross Alpha lx 107 4 4 1 P Q Sr-89, Sr-90 5x10 8 2

Each Batch Composite ( )

-~ I t 1*

3

2. Continuous Continuous ( ) W Principal Composite 3

( ) Gamma 5x1107 Releases Emitters (6)

(VUCDT

......... di~h-aFge, CWWTS outlet and Turbine Building Sump to RC)(5) 1-131 lx1 0-6 M M Dissolved and Grab Sample Entrained lx10 5 Gases (Gamma emitters )(7)

Continuous(3) M H-3 1x1005 Composite (3)

Gross Alpha lx1007 3

Continuous ( ) Q Sr-89, Sr-90 5x1 0-8 3

Composite ( )

McGuire Units 1 and 2 16.11.1-2 Revision 112

Liquid Effluents - Concentration 16.11.1 TABLE 16.11.1-1 (Page 2 of 3)

NOTES:

(1) The LLD is defined, for purposes of these commitments, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

LLD 4.66sb E. V .2.22 x 106 -Y . exp (-2At)

Where:

LLD is the "a priori" lower limit of detection as defined above (as microCurie per unit mass or volume),

....... Stizi-thez~standard-de-v~iaton~o~f~th~e~bac kgro.u-d*-*.ouritii-g-ra-teo-*r=Q*-i,-f bc-uano-f . "

a blank sample as appropriate (as counts per minute),

SE is the counting efficiency (as counts per disintegration),

V is the sample size (in units of mass or volume),

2.22 x 106 is the number of disintegrations per minute per microCurie, Y is the fractional radiochemical yield (when applicable),

X is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).

Typical values of E, V, Y and At shall be used in the calculation.

It should be recognized that the LLD is defined as an a driori(before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

(2) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

McGuire Units 1 and 2 16.11.1-3 Revision 112

Liquid Effluents - Concentration 16.11.1 TABLE 16.11.1-1 (Page 3 of 3)

(3) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously or intermittently in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

(4) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated and thoroughly mixed to assure representative sampling.

(5) A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g.,

from a volume of system that has an input flow during the continuous release.

(6) The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141. The LLD for Ce-144 is 5x10-6 microCi/ml. This list does not mean that only these nuclides are to'be detected and reported. Other peaks which are measurable and

. "ide-tir b-e _-tee Annual Radioactive Effluent Release Report.

. (7) The principal gas gamma emitters for which the LLD specification applies are Xe-1 33 and Xe-135. These are the reference nuclides in Regulatory Guide 1.21.

McGuire Units 1 and 2 ', 16.11.1-4 Revision 112

Liquid Effluents - Concentration 16.11.1 FIGURE 16.11.1-1 SITE BOUNDARY/ EXCLUSION AREA BOUNDARY McGuire Units 1 and 2 16.11.1-5 Revision 112 1~

Liquid Effluents - Concentration 16.11.1

. BASES This commitment is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than 10 times the effluent concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.

This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within: (1) the Section II.A design objectives of Appendix 1,10 CFR Part 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.1301 to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-1 35 is the controlling radioisotope and its EC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2. This commitment applies to the release of liquid effluents from all reactors at the site.

The basic requirements for the Selected Licensee Commitments concerning effluents from nuclear power reactors are stated in 10CFR50.36a. These requirements indicate that compliance with effluent Selected Licensee.Commitments will keep average annual releases of radioactive material in effluents to small percentages of the limits specified in the old 10CFR20.106 (new 10CFR20.1301). These requirements further indicate that

-operational flexibility is allowed, compatible with considerations of health and safety, which

may tempo rarily-result-in-releases-higher-thapn-such-,sma-percentages-but- still-within -the --

limits specified in the old 10CFR20.106 which references Appendix B, Table II concentrations (MPCs). These referenced concentrations are specific values which relate to

  • an annual dose of 500 mrem. It is further indicated in 10CFR50.36a that when using operational flexibility, best efforts shall be exerted to keep levels of radioactive materials in effluents as low as is reasonably achievable (ALARA) as set forth in 10CFR50, Appendix I.

As stated in the Introduction to Appendix B of the new 10CFR20, the effluent concentration

_-- . (EC) -limits-given -in Appendix-B,-Table2, -Column -2_are-based-on-an-annual.dose-of-50 mrem. Since a release concentration corresp*onding toa limiting dose rate Of 500 mrem/year has been acceptable as a SLC limit for liquid effluents, which applies at all times as an assurance that the limits of 10CFR50, Appendix I are not likely to be exceeded, it should not be necessary to reduce this limit by a factor of 10.

Operational history at Catawba/McGuire/Oconee has demonstrated that the use of the concentration values associated with the old 10CFR20.106 as SLC limits has resulted in calculated maximum individual doses to members of the public that are small percentages of the limits of 10CFR50, Appendix I. Therefore, the use of concentration values which correspond to an annual dose of 500 mrem should not have a negative impact on the ability to continue to operate within the limits of 10CFR50 Appendix I and 40CFR190.

Having sufficient operational flexibility is especially important in establishing a basis for effluent monitor setpoint calculations. As discussed above, the concentrations stated in the new 10CFR20, Appendix B, Table 2, Column 2, relate to a dose of 50 mrem in a year.

When applied on an instantaneous basis, this corresponds to a dose rate of 50 mrem/year.

This low value is impractical upon which to base effluent monitor setpoint calculations for many liquid effluent release situations when monitor background, monitor sensitivity, and monitor performance must be taken into account.

BASES (continued)

McGuire Units 1 and 2 16.11.1-6 Revision 112

Liquid Effluents - Concentration 16.11.1 Therefore, to accommodate operational flexibility needed for effluent releases, the limits associated with SLC 16.11.1 are based on ten times the concentrations stated in the new 10CFR20, Appendix B, Table 2, Column 2 to apply at all times. The multiplier of ten is proposed because the annual dose of 500 mrem, upon which the concentrations in the old 10CFR20, Appendix B, Table II, Column 2 are based, is a factor of ten higher than the annual dose of 50 mrem, upon which the concentrations in the new 10CFR20, Appendix B, Table 2, Column 2, are based. Compliance with the limits of the new 10CFR20.1301 will be demonstrated by operating within the limits of 10CFR50, Appendix I and 40CFR190.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination -

Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K.,

"Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

REFERENCES

1. McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)
2. International Commission on Radiological Protection (ICRP) Publication 2 McGuire Units 1 and 2 16.11.1-7 Revision 112

Dose Rate - Gaseous Effluents 16.11.6 16.11 RADIOLOGICAL EFFLUENT CONTROL 16.11.6 Dose Rate - Gaseous Effluents COMMITMENT The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figurel6.11.1-1) shall be limited to the following:

a. For noble gases: < 500 mrem/yr to the whole body and < 3000 mrem/yr to the skin, and
b. For Iodine - 131 and 133, for tritium, and for all radioactive materials in particulate form with half-lives greater than 8 days:

< 1500 mrem/yr to any organ.

APPLICABILITY At all times.

REMEDIAL ACTIONS .

CONDITION REQUIRED ACTION COMPLETION TIME A. Dose rate not within A.1 Restore the release rate to Immediately limit, within limits.

TESTING REQUIREMENTS TEST FREQUENCY TR 16.11.6.1 Verify dose rates due to noble gases in gaseous effluents In accordance with are within limits in accordance with the methodology and the ODCM parameters in the ODCM.

TR 16.1 l$.6.2 Verify dose rates due to radioactive materials, other than In accordance with noble gases, in gaseous effluents are within limits in Table 16.11.6-1 accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with Table16.11.6-1.

McGuire Units 1 and 2 16.11.6-1 Revision 112

I Dose Rate - Gaseous Eiits 16.11.6 TABLE 16.11.6-1*

(Page 1 of 4)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Release Type Sampling Frequency Minimum Analysis Type of Activity Analysis Lower Limit of.

Frequency Detection (LLD)(1 )

___ (lCi/ml)

1. Waste Gas Storage Tanks P P Each Tank Each Tank I Principal Gas Gamma Emitters(6) lx104 Grab Sample
2. Containment Purge P P 61 Each PURGE Each PURGE Principal Gas Gamma Emitters~ lx1 Grab Sample _

M H-3 lxi0o

3. Unit Vent W~z* W Principal Gas Gamma Emitters{b lx104 Grab Sample H-3 lx10-6 4.a. Radwaste Facility Vent W W Principal Gas Gamma Emitters{b) lx104
b. Waste Handling Building Grab Sample
c. Equipment Staging Building H-3 lx10"*
5. Unit Vents Continuous* WN1 1-131 lx1lOz Charcoal Sample 1-133 lx10"lO Continuous N' -WN' Principal Gamma Emitterstu) lx10-1 Particulate (1-131, Others)

Sample Continuous(b) M Gross Alpha") 1x10" Composite Particulate Sample Continuous1 Y Q Sr-89, Sr-90 lx10-11 Composite Particulate Sample McGuire Units 1 and 2 16.11.6-2 Revision 112

Dose Rate - Gaseous E ts 16.11.6 TABLE 16.11.6-1 (Page 2 of 4)

RADIOACTIVE GASEOUS WASTE SAMPLINC. AND ANALYSIS PROGRAM Gaseous Release Type Sampling Frequency Minimum Analysis Type of Activity Analysis Lower Limit of Frequency Detection (LLD)(1 )

(liCi/ml)

6. All Release Types as listed in 4 above. Continuous(b) W 1-131 lx10-1 Charcoal Sample 1-133 1xlo0"u Continuous N) W" Principal Gamma Emitters(f) 1x10"-1 Particulate (1-131, Others)

Sample Continuous N M Gross Alphav) lx101 Composite Particulate Sample Continuous*=) Q I Sr-89, Sr-90 lxi0" Composite Particulate Sample McGuire Units 1 and 2 16.1 1.6-3 Revision 112

Dose Rate - Gaseous Effluents 16.11.6 TABLE 16.11.6-1 (Page 3 of 4)

NOTES:

1. The LLD is defined, for purposes of these commitments, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

LLD = 4"66sb E. V. 2.22 x 106

  • Y. exp (-2At)

Where:

LLD = the "a priori" lower limit of detection as defined above (as microCurie per unit mass or volume);

_Sb- =- thes[anddrd-dýiitiv fthbak6-countinga~f-b counting rate of a blank sample as appropriate (as counts per minute);

  • E = the counting efficiency (as counts per disintegration);

V = the sample size (in units of mass or volume);

2.22 xl06 = the number of disintegrations per minute per microCurie; Y = the fractional radiochemical yield (when applicable);

= the radioactive decay constant for the particular radionuclide; and At = the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).

Typical values of E, V, Y and At shall be used in the calculation.

It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement.

McGuire Units 1 and 2 16.11.6-4 Revision 112

Dose Rate - Gaseous Effluents 16.11.6 TABLE 16.11.6-1 (Page 4 of 4)

NOTES:

2. Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.
3. Not used.
4. Not used.
5. The ratio of the sample flow volume to the sampled stream flow volume shall be known for the time period covered by each dose or dose rate calculation made in accordance with SLCs 16.11.6, 16.11.8 and 16.11.9.
6. The principal gamma emitters for which the. LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, 1-131, Cs-134, Cs-137, and Ce-141 in iodine and particulate releases. The LLD for Ce-144 is 5x10-9 microCi/ml.

_-- This.isLd-oes.rmean-that-only-theseaiucGides-are-tobe-co~nsidered -Qtther-gamma* -

- eaks--thaf-ae -idenMtiabl&-,-t-og-th-e-r-With-those of -the-abo6ve t-n

-id ----,---ha-lal-lo-be ..

analyzed and reported in the Annual Radioactive Effluent Release Report.

7. 'The composite filter(s) will be analyzed for alpha activity by analyzing the filter media used during the collection period.
8. Samples shall be changed at least once per 7 days and analyses shall be completed to meet LLD after' changing, or after removal from sampler. If the particulate and charcoal sample frequency is changed to a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> frequency the corresponding LLDs may be increased by a factor of 10 (i.e., LLD for 1-131 from 1 x 10-12 to 1 x 10 1 microCi/ml).

McGuire Units 1 and 2 16.11.6-5 Revision 112

Dose Rate - Gaseous Effluents 16.11.6 BASES 0 Specific release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the whole body, and 3000 mrem/year to the skin from noble gases, and 1500 mrem/year to any organ from Iodine 131, Iodine 133, tritium, and all radionuclides in particulate form with half-lives greater than eight days. This commitment applies to the release of gaseous effluents from all reactors at the site. The Exclusion Area Boundary (Site Boundary) is set as the boundary for gaseous effluent release limits. The Exclusion Area Boundary (EAB) is formed by a 2500 ft radius centered on the Reactor Buildings' centerlines as shown on Figure 16.11.1-1.

The basic requirements for the Selected Licensee Commitments concerning effluents from nuclear power reactors are stated in 10CFR50.36a. These requirements indicate that compliance with effluent Selected Licensee Commitments will keep average annual releases of radioactive material in effluents to small percentages of the limits specified in the old 10CFR20.106 (new IOCFR20.1301). These requirements further indicate that operational flexibility is allowed, compatible with considerations of health and safety, which may temporarily result in releases higher than such small percentages, but still within the limits specified in the old 10CFR20.106 which references Appendix B, Table II concentrations (MPCs). These referenced concentrations are specificvalues which relate to

... - n naLdos-e-ot5DOjnr u zmr*_is-furtherJndicatedjn--*)IOCFR50*,3_6 aAthaLwhen.using--.

operational flexibility, best efforts shall be exerted to keep levels of radioactive materials in effluents as low as is reasonably achievable (ALARA) as set forth in 10CFR50, Appendix I.

. As stated in the Introduction to Appendix B of the new 10CFR20, the effluent concentration (EC) limits given in Appendix B, Table 2, Column 1, are based on an annual dose of 50 mrem for isotopes for which inhalation or ingestion is limiting or 100 mrem for isotopes for which submersion (noble gases) is limiting. Since release concentrations corresponding to limiting dose rates of less than or equal to 500 mrem/year to the whole body, 3000 mrem/year to the skin from noble gases, and 1500 mrem/year to any organ from Iodine 131, Iodine 133, tritium and for all radionuclides in particulate form with half-lives greater than eight days at the site boundary has been acceptable as a SLC limit for gaseous effluents to

.assure that the limits of 10CFR50, Appendix I and 40CFR190 are not likely to be exceeded, it should not be necessary to restrict the operational flexibility by incorporating the EC value for isotopes based on ingestion/inhalation (50 mrem/year) or for isotopes with the EC based on submersion (100 mrem/year).

Having sufficient operational flexibility is especially important in establishing a basis for effluent monitor setpoint calculations. As discussed above, the concentrations stated in the new 10CFR20, Appendix B, Table 2, Column 1, relate to a dose of 50 or 100 mrem in a year. When applied on an instantaneous basis, this corresponds to a dose rate of either 50 or 100 mrem/year. These low values are impractical upon which to base effluent monitor setpoint calculations for many effluent release situations when monitor background, monitor sensitivity, and monitor performance must be taken into account. Therefore, to accommodate operational flexibility needed for effluent releases, the limits associated with SLC 16.11.6 will be maintained at the current dose rate limit for noble gases of 500 mrem/year to the whole body and 3000 mrem/year to the skin, for Iodine 131, Iodine 133, tritium and all radionuclides in particulate form with half-lives greater than eight days an instantaneous dose rate limit of 1500 mrem/year to any organ.

McGuire Units 1 and 2 16.11.6-6 Revision 112

Dose Rate - Gaseous Effluents 16.11.6 BASES (continued)

. Compliance with the limits of the new 10CFR20.1301 will be demonstrated by operating within the limits of 10CFR50, Appendix I and 40CFR190. Operational history at Catawba/McGuire/Oconee has demonstrated that the use of the dose rate values listed above (i.e. 500 mrem/year, 3000 mrem/year and 1500 mrem/year) as SLC limits has resulted in calculated maximum individual doses to members of the public that are small percentages of the limits of 10CFR50, Appendix I and 40CFR1 90.

The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., "Limits for Qualitative Detection and Quantitative Determination -

Application to Radiochemistry," Anal. Chem. 40, 586-93. (1968), and Hartwell, J. K.

"Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

REFERENCES

1. McGuire Nuclear Station, Off site Dose Calculation Manual
2. 10 CFR Part 20, Appendix B
3. 10 CFR Part 20 O 4. 10 CFR Part 50 McGuire Units 1 and 2 16.11.6-7 Revision 112
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