ML030770092

TS Pages to Amendment 132 of License NPF-47

ML030770092
Person / Time
Site:	River Bend
Issue date:	03/14/2003
From:	Michael Webb NRC/NRR/DLPM/LPD4
To:	Hinnenkamp P Entergy Operations
Webb M, NRR/DLPM, 415-1347
Shared Package
ml030760789	List: ML030770092
References
RG-1.183, TAC MB5021
Download: ML030770092 (25)

Text

Definitions 1.1 1.1 Definitions (continued)

CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY, including required alarm, interlock, display, and trip functions, and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is tested.

CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel.

The following exceptions are not considered to be CORE ALTERATIONS:

a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement); and

b. Control rod movement provided there are no fuel assemblies in the associated core cell.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE OPERATING LIMITS The COLR is the unit specific document that provides cycle REPORT (COLR) specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132,1-133,1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Federal Guidance Report (FGR) 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," 1989.

(continued)

RIVER BEND 1.0-2 Amendment No. 8--, 132

CRFA System Instrumentation 3.3.7.1 Table 337.1-1 (page 1 of 1)

Control Room Fresh Air System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION A1 REQUIREMENTS VALUE Reactor Vessel Water Level - 1,2.3 2 B SR 33711 -47 inches Low Low, Level 2 SR 33712 SR 33713 SR 33714 SR 33715 2 Drywell Pressure - High 1,2,3 2 C SR 337.11

• 188 psid SR 33712 SR 33713 SR 33714 SR 33715 3 Control Room Local Intake 1.2,3 1 D SR 33711 < 097 x 10-5 Ventilation Radiation Monitors (a),(b) SR 337.1 2 pCi/cc SR 33714 SR 33715 (a) During operations with a potential for draining the reactor vessel (b) During movement of recently irradiated fuel assemblies in the pnmary containment or fuel building RIVER BEND 3.3-71 Amendment No. 94-I-449, 132

Primary Containment Air Locks 3.6.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.2.1 - ------ NOTES

1. An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

2. Results shall be evaluated against acceptance criteria applicable to SR 3.6.1.1.1.

Perform required primary containment air lock In accordance with leakage rate testing in accordance with the Primary the Primary Containment Leakage Rate Testing Program. Containment Leakage Rate Testing Program I SR 3.6.1.2.2 Verify primary containment air lock seal 7 days air flask pressure is Ž_90 psig.

SR 3.6.1.2.3 ---------- NOTE Only required to be performed upon entry or exit through the primary containment air lock.

Verify only one door in the primary containment air 184 days lock can be opened at a time.

(continued)

RIVER BEND 3.6-7 Amendment No. 8--84, 132

Primary Containment Air Locks 3.6.1.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.2.4 Verify, from an initial pressure of 18 months 90 psig, the primary containment air lock seal pneumatic system pressure does not decay at a rate equivalent to

> 1.50 psig for a period of 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />. I RIVER BEND 3.6-8 Amendment No. 84-, 1i2

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.8 Verify in-leakage rate of_< 340 scfh for each of the 18 months following valve groups when tested at 11.5 psid for MS-PLCS valves.

a. Division I MS-PLCS valves

b. Division II MS-PLCS valves SR 3.6.1.3.9 ------- NOTE T ------

Only required to be met in MODES 1, 2, and 3.

Verify the combined leakage rate for all secondary In accordance with containment bypass leakage paths is < 580,000 the Primary I cc/hr when pressurized to > Pa. Containment Leakage Rate Testing Program (continued)

RIVER BEND 3.6-18 Amendment No. 81-84 08, 132

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.10 --NOTE -.---

Only required to be met in MODES 1, 2, and 3.

Verify leakage rate through each main steam line In accordance is _<50 scfh when tested at > Pa, and the total with the Primary leakage rate through the valves served by each Containment division of MS-PLCS is < 150 scfh per division Leakage Rate Testing Program when tested at > Pa.

SR 3.6.1.3.11 --------- NOTE---- ..

Only required to be met in MODES 1, 2, and 3.

Verify combined leakage rate through In accordance with hydrostatically tested lines that penetrate the the Primary primary containment is within limits. Containment Leakage Rate Testing Program (continued)

RIVER BEND 3.6-19 Amendment No. 81-84,132

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.12 Deleted.

I RIVER BEND 3.6-20 Amendment No. 8484, 132

Secondary Containment-Operating 3.6.4.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.4.1.2 Verify all secondary containment equipment 31 days hatches are closed and sealed and loop seals filled.

SR 3.6.4.1.3 Verify each secondary containment access door is 31 days closed, except when the access opening is being used for entry and exit.

SR 3.6.4.1.4 Verify each standby gas treatment (SGT) 18 months on subsystem will draw down the shield building a STAGGERED annulus and auxiliary building to > 0.5 and TEST BASIS

> 0.25 inch of vacuum water gauge in _ 18.5 and

< 34.5 seconds, respectively. I SR 3.6.4.1.5 Deleted Not Applicable 18 months on a SR 3.6.4.1.6 Verify each SGT subsystem can maintain > 0.5 STAGGERED and > 0.25 inch of vacuum water gauge in the TEST BASIS shield building annulus and auxiliary building, respectively, for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

SR 3.6.4.1.7 Deleted Not Applicable RIVER BEND 3.6-47 Amendment No. 84- 98 443, 132

Drywell 3.6.5.1 3.6 CONTAINMENT SYSTEMS 3.6.5.1 Drywell LCO 3.6.5.1 The drywell shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drywell inoperable. A.1 Restore drywell to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> associated Completion Time not met AND B.2 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5.1.1 Verify personnel door inflatable seal air flask 7 days pressure _> 75 psig.

SR 3.6.5.1.2 Verify from an initial pressure of 75 psig, the 18 months personnel door inflatable seal pneumatic system pressure does not decay at a rate equivalent to

> 20.0 psig for a period of 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />. I (continued)

RIVER BEND 3.6-60 Amendment No. 84, 132

Drywell Air Lock 3.6.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5.2.1 Deleted SR 3.6.5.2.2 Verify drywell air lock seal air flask pressure is 7 days

>75 psig.

SR 3.6.5.2.3 NOTE Only required to be performed upon entry into drywell.

Verify only one door in the drywell air lock can be 24 months opened at a time.

SR 3.6.5.2.4 Deleted SR 3.6.5.2.5 Verify, from an initial pressure of 75 psig, the 18 months drywell air lock seal pneumatic system pressure does not decay at a rate equivalent to > 20.0 psig I for a period of 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />.

RIVER BEND 3.6-66 Amendment No. 8-1 87, 132

CRFA System 3.7.2 3.7 PLANT SYSTEM 3.7.2 Control Room Fresh Air (CRFA) System LCO 3.7.2 Two CRFA subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the primary I containment, or fuel building.

During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CRFA subsystem A.1 Restore CRFA subsystem 7 days inoperable, to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> Associated Completion Time of Condition A not AND met in MODE 1, 2, or 3.

B.2 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> (continued)

RIVER BEND 3.7-5 Amendment No. 8-144-9,132

CRFA System 3.7.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and --- NOTE associated Completion LCO 3.0.3 is not applicable.

Time of Condition A not ----

met during movement of recently irradiated fuel C.1 Place OPERABLE Immediately assemblies in the primary CRFA subsystem in containment or fuel emergency mode.

building or during OPDRVs. OR C.2.1 Suspend movement of Immediately recently irradiated fuel assemblies in the primary containment and fuel building.

AND C.2.2 Initiate action to Immediately suspend OPDRVs.

D. Two CRFA subsystems D.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, or 3.

(continued)

RIVER BEND 3.7-6 Amendment No. 84- 44-, 132

CRFA System 3.7.2 ACTIONS (continued) I_

CONDITION REQUIRED ACTION COMPLETION TIME E. Two CRFA subsystems E.1 Suspend movement of Immediately inoperable during recently irradiated fuel movement of recently assemblies in the primary irradiated fuel assemblies containment and fuel in the primary containment building.

or fuel building, or during OPDRVs. AND E.2 Initiate action to suspend Immediately OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 Operate each CRFA subsystem for > 10 continuous 31 days hours with the heaters operating.

SR 3.7.2.2 Perform required CRFA filter testing in accordance In accordance with with the Ventilation Filter Testing Program (VFTP). the VFTP SR 3.7.2.3 Verify each CRFA subsystem actuates on an actual 18 months or simulated initiation signal.

(continued)

RIVER BEND 3.7-7 Amendment No. 84- 4-1-9, 132

Control Room AC System 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Control Room Air Conditioning (AC) System LCO 3.7.3 Two control room AC subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the primary I containment or fuel building.

During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One control room AC A.1 Restore control room AC 30 days subsystem inoperable, subsystem to OPERABLE status.

B. Two control room AC B.1 Verify control room area Once per 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> subsystems inoperable, temperature < 104 0 F.

AND B.2 Restore one control room AC 7 days subsystem to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> Associated Completion Time of Condition A or B AND not met in MODE 1, 2, or 3. C.2 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> (continued)

RIVER BEND 3.7-9 Amendment No. 84-44-9, 132

Control Room AC System 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and .NOTE .

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A not met during movement of recently irradiated fuel D.1 Place OPERABLE control Immediately assemblies in the primary room AC subsystem in containment or fuel operation.

building, or during OPDRVs. OR D.2.1 Suspend movement of Immediately recently irradiated fuel assemblies in the primary containment and fuel building.

AND D.2.2 Initiate action to Immediately suspend OPDRVs.

(continued)

RIVER BEND 3.7-10 Amendment No. 84-44-9, 132

Control Room AC System 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E.1 Suspend movement of Immediately associated Completion recently irradiated fuel Time of Condition B not assemblies in the primary met during movement of containment and fuel recently irradiated fuel building.

assemblies in the primary containment or fuel AND building, or during OPDRVs. E.2 Initiate action to suspend Immediately OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify each control room AC subsystem has the 18 months capability to remove the assumed heat load.

RIVER BEND 3.7-11 Amendment No.84-449, 132

AC Sources-Shutdown 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources-Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a. One qualified circuit between the offsite transmission network and the onsite Class 1 E AC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems-Shutdown";

b. One diesel generator (DG) capable of supplying one division of the Division I or II onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10; and

c. One qualified circuit, other than the circuit in LCO 3.8.2.a, between the offsite transmission and the Division Ill onsite Class 1E electrical power distribution subsystem, or the Division III DG capable of supplying the Division III onsite Class 1E AC electrical power distribution subsystem, when the Division III onsite Class 1 E electrical power distribution subsystem is required by LCO 3.8.10.

APPLICABILITY: MODES 4 and 5, During movement of recently irradiated fuel assemblies in the primary containment or fuel building.

RIVER BEND 3.8-17 Amendment No. 8I-05, 132

AC Sources-Shutdown 3.8.2 ACTIONS L I .,*-r.

I Ir--------------

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. LCO Item a not met. ------ NOTE Enter applicable Condition and Required Actions of LCO 3.8.10, when any required division is de-energized as a result of Condition A.

A.1 Declare affected Immediately required feature(s) with no offsite power available from a required circuit inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately recently irradiated fuel assemblies in the primary containment and fuel building.

AND A.2.3 Initiate action to Immediately suspend operations with a potential for draining the reactor vessel (OPDRVs).

AND (continued)

RIVER BEND 3.8-18 Amendment No. 8-1-, 132

AC Sources-Shutdown 3.8.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.4 Initiate action to restore Immediately required offsite power circuit to OPERABLE status.

B. LCO Item b not met. B.1 Suspend CORE Immediately ALTERATIONS.

AND Immediately B.2 Suspend movement of recently irradiated fuel assemblies in primary containment and fuel building.

AND Immediately B.3 Initiate action to suspend OPDRVs.

AND Immediately B.4 Initiate action to restore required DG to OPERABLE status.

C. LCO Item c not met. C.1 Declare High Pressure 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> Core Spray System and Standby Service Water System pump 2C inoperable.

RIVER BEND 3.8-19 Amendment No. 81, 132

DC Sources-Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources-Shutdown LCO 3.8.5 The following shall be OPERABLE:

a. One Class 1 E DC electrical power subsystem capable of supplying one division of the Division I or II onsite Class 1E DC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems-Shutdown";

b. One Class I E battery or battery charger, other than the DC electrical power subsystem in LCO 3.8.5.a, capable of supplying the remaining Division I or II onsite Class 1 E DC electrical power distribution subsystem(s) when required by LCO 3.8.10; and

c. The Division III DC electrical power subsystem capable of supplying the Division III onsite Class 1 E DC electrical power distribution subsystem, when the Division Ill onsite Class 1E DC electrical power distribution subsystem is required by LCO 3.8.10.

APPLICABILITY: MODES 4 and 5, During movement of recently irradiated fuel assemblies in the primary containment or fuel building.

RIVER BEND 3.8-28 Amendment No. 8-1-, 132

DC Sources-Shutdown 3.8.5 ACTIONS

-NOTE LCO 3.0.3 is not applicable CONDITION I REQUIRED ACTION ICOMPLETION TIME A. One or more required DC A.1 Declare affected Immediately electrical power required feature(s) subsystems inoperable. inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A 2.2 Suspend movement of Immediately recently irradiated fuel assemblies in the primary containment and fuel building.

AND A.2.3 Initiate action to Immediately suspend operations with a potential for draining the reactor vessel.

AND A.2.4 Initiate action to restore Immediately required DC electrical power subsystems to OPERABLE status.

I ______________________

RIVER BEND 3.8-29 Amendment No. 8-1-, 132

Inverters-Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Inverters-Shutdown LCO 3.8.8 One Divisional inverter shall be OPERABLE capable of supplying one division of the Division I or II onsite Class 1E uninterruptible AC vital bus electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems-Shutdown".

APPLICABILITY: MODES 4 and 5, During movement of recently irradiated fuel assemblies in the primary I containment or fuel building.

ACTIONS LCO 3.0.3 is not applicable CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare affected Immediately inverters inoperable, required feature(s) inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend handling of Immediately recently irradiated fuel assemblies in the primary containment or fuel building.

AND (continued)

RIVER BEND 3.8-36 Amendment No. 8-1-, 132

Distribution Systems-Shutdown 3.8.10 3.8 ELECTRICAL POWER SYSTEMS 3.8.10 Distribution Systems-Shutdown LCO 3.8.10 The necessary portions of the Division I, Division II, and Division III AC, DC, and Division I and II AC vital bus electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.

APPLICABILITY: MODES 4 and 5, During movement of recently irradiated fuel assemblies in the primary I containment or fuel building.

ACTIONS I I----------------------

LCO 3.0.3 is not applicable CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare associated Immediately AC, DC, or AC vital bus supported required electrical power feature(s) inoperable.

distribution subsystems inoperable. OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately recently irradiated fuel assemblies in the primary containment and fuel building.

AND (continued)

RIVER BEND 3.8-41 Amendment No. 84-, 132

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Ventilation Filter Testing Program (VFTP) (continued)

b. Demonstrate for each of the ESF systems that an inplace test of the charcoal adsorber shows a penetration and system bypass < 0.05% when tested in accordance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1989 at the system flowrate specified below +/- 10%:

ESF Ventilation System Flowrate SGTS 12,500 cfm FBVS 10,000 cfm CRFAS 4,000 cfm

c. Demonstrate for each of the ESF systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory Guide 1.52, Revision 2, shows the methyl iodide penetration less than the value specified below when tested in accordance with ASTM D3803-1989 at a temperature of 30 0 C and the relative humidity specified below:

ESF Ventilation System Penetration RH SGTS 5.0% 70% I FBVS 0.5% 70% I CRFAS 1.0% 70%

d. Demonstrate for each of the ESF systems that the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers is less than the value specified below when tested in accordance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1989 at the system flowrate specified below +/- 10%:

ESF Ventilation System Delta P Flowrate SGTS < 8" WG 12,500 cfm FBVS < 8" WG 10,000 cfm CRFAS < 8" WG 4,000 cfm (continued)

RIVER BEND 5.0-12 Amendment No. 84- 445, 132

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Technical Specifications (TS) Bases Control Program (continued)

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the USAR.

d. Proposed changes that do not meet the criteria of either Specification 5.5.11 .b.1 or Specification 5.5.11 .b.2 above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

5.5.12 DELETED 5.5.13 Primary Containment Leakage Rate Testing Progqram A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, except that the next Type A test performed after the August 15, 1992, Type A test shall be performed no later than August 14, 2007.

The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 7.6 psig.

The maximum allowable primary containment leakage rate, La, at Pa, shall be 0.325% of primary containment air weight per day.

The Primary Containment leakage rate acceptance criterion is < 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type B and Type C tests and < 0.75 La for Type A tests.

The provisions of SR 3.0.2 do not apply to test frequencies specified in the Primary Containment Leakage Rate Testing Program.

The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

RIVER BEND 5.0-16 Amendment No. 84-I84-54-4-, 132