ML070740673

Units, 1 and 2, Tech Spec Pages for Amendments 250 and 230 Regarding Technical Specification Changes Per Generic Safety Issue (GSI) 191

ML070740673
Person / Time
Site:	North Anna
Issue date:	03/13/2007
From:	NRC/NRR/ADRO/DORL/LPLII-1
To:
Lingam, Siva NRR/DORL 415-1564
Shared Package
ML070740367	List: ML070720043 ML070740673
References
GSI-191, TAC MD3197, TAC MD3198
Download: ML070740673 (9)

Text

.3-(2) Pursuant to the Act and 10 CFR Part 70, VEPCO to receive, possess, and use at any time special nuclear material as reactor fuel, In accordance with the limitations for storage and amounts required for reactor operation, as described In the Updated Final Safety Analysis Report; (3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, VEPCO to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor Instrumentation and radiation monitoring equipment calibration, and as fission detectors In amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30,40, and 70, VEPCO to receive, possess, and use In amounts as required any byproduct, source, or special nuclear material, without restriction to chemical or physical form, for sample analysis or Instrument calibration or associated with radioactive apparatus or component; and (5) Pursuant to the Act and 10 CFR Parts 30 and 70, VEPCO to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified In the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; Is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and Is'subject to the additional conditions specified or Incorporated below.

(1) Maximum Power Level VEPCO Is authorized to operate the North Anna Power Station, Unit No. 1, at reactor core power levels not In excess of 2893 megawatts (thermal).

(2) Technical Specifications The Technical Specifications contained InAppendix A, as revised through Amendment No. 250 are hereby Incorporated In the renewed license.

The licensee shag operate the faclity in accordance with the Technical Specifications..

Renewed License No. NPF-4 Amendment No. 250

(3) Pursuant to the Act and 10 CFR Parts 30,40, and 70, VEPCO to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors In amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, VEPCO to receive, possess, and use Inamounts as required any byproduct, source, or special nuclear material, without restriction to chemical or physical form, for sample analysis or Instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, VEPCO to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C.' This renewed license shall be deemed to contain and Is subject to the conditions specified In the Commission's regulations as set forth In 10 CFR Chapter Iand Is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and Is subject to the additional conditions specified or Incorporated below-.

(1) Maximum Power Level VEPCO Isauthorized to operate the facility at steady state reactor care power levels not Inexcess of 2893 megawatts (thermal).

(2) Technical SDecifications The Technical Specirications contained InAppendix A.as revised through Amendment No. 230 are hereby Incorporated In the renewed license.

The licensee shaii operate the facility Inaccordance with theTechnical Specifications.

(3) Addditional Conditions The matters specified Inthe following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the Issuance of the condition or within the operational restrictions Indicated. The removal of thesd conditions shall be made by an amendment to the renewed license supported by a favorable evaluation by the Commission:

a. IfVEPCO plans to remove or to make significant changes In the normal operation of equipment that controls the amount of radioactivity In effluents from the North Anna Power Station. the Renewed Ucense No NPF-7

.Amendment No. 230

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 2 of 4)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS ALLOWABLE VALUE

2. Containment Spray Systems I

a. Manual Initiation 1, 2. 3, 4 2 per train, B SR 3.3.2.7 NA 2 trains

b. Automatic Actuation Logic 1, 2. 3. 4 2 trains C SR 3.3.2.2 NA and Actuation Relays SR 3.3.2.3 SR 3.3.2.5

c. Containment Pressure High High 1. 2. 3 4 E SR 3.3.2.1 < 28.45 psia SR 3.3.2.4 SR 3.3.2.8 SR 3.3.2.9

d. Refueling Water Storage Tank I

1. 2, 3 3 D SR 3.3.2.1 2 59% and (RWST) Level-Low SR 3.3.2.4  : 61%

SR 3.3.2.8 SR 3.3.2.9 Coincident with Containment Refer to Function 2.c (Containment Spray-Containment Pressure-High High)

Pressure-High High for all functions and requirements.

3. Containment Isolation

a. Phase A Isolation (1) Manual Initiation 1, 2. 3, 4 2 B SR 3.3.2.7 NA (2) Automatic Actuation 1. 2, 3, 4 2 t rains C SR 3.3.2.2 NA Logic and Actuation SR 3.3.2.3 Relays SR 3.3.2.5 (3) Safety Injection Refer to Function 1 ( Safety Injection) for all initiation functions and requirements.

b. Phase B Isolation (1) Manual Initiation Refer to Function 2.a (Containment Spray-Manual Initiation) for all functions and requirements.

(2) Automatic Actuation 1, 2. 3. 4 2 trains C SR 3.3.2.2 NA Logic and Actuation SR 3.3.2.3 Relays SR 3.3.2.5 (3) Containment Pressure High High Refer to Function 2.c (Containment Spray-Containment Pressure High High) for all functions and requirements.

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ESFAS Instrumentation 3.3.2

'Table 3.3.2-1 (page 4 of 4)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE

6. Auxiliary Feedwater

a. Automatic Actuation Logic 1, 2. 3 2 trains G SR 3.3.Z.2 NA and Actuation Relays SR 3.3.2.3 SR 3.3.2.5

b. SG Water Level-Low Low 1. 2, 3 3 per SG D SR 3.3.2.1 > 17%

SR 3.3.2.4 SR 3.3.2.8 SR 3.3.2.9

c. Safety Injection Refer to Function I (Safety Injection) for all initiation functions and requirements.

d. Loss of Offsite Power 1. 2. 3 1 per bus. F SR 3.3.2.6 2184 V 2 buses SR 3.3.2.8 SR 3.3.2.9

e. Trip of all Main Feedwater 1, 2 2 per pump H SR 3.3.2.7 NA Pumps SR 3.3.2.9

7. Automatic Switchover to Containment Sump

a. Automatic Actuation Logic 1, 2, 3, 4 2 trains C SR 3.3.2.2 NA and Actuation Relays SR 3.3.2.3 SR 3.3.2.5

b. RWST Level-Low Low , 4 4 1 SR 3.3.2.1 ;e 15% and

1. 23, SR SR 3.3.2.4 3.3.2.8

17% I SR 3.3.2.9 Coincident with Safety Refer to Function 1 (Safety Injection) for all initiation functions and Injection requirements.

8. ESFAS Interlocks

a. Reactor Trip, P-4 1, 2, 3 1 per train, F SR 3.3.2.7 NA 2 trains

b. Pressurizer Pressure, P-11 1. 2, 3 3 J SR ý3.3.2.1 < 2010 psig SR 3.3.2.8

c. Tavg-Low Low. P-12 1. 2. 3 1 per loop J SR :3.3.2.1  ; 5429F and SR :3.3.2.8 < 5450F N'-or Anna Units I and 2 *,. ,J *,

.)L-1.1 11 Amendment Nos. 250, 230.

ECCS-Operating 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.5 Verify each ECCS automatic valve in the 18 months flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal'.

SR 3.5.2.6 Verify each ECCS pump capable of starting 18 months automatically starts automatically on an actual or simulated actuation signal.

SR 3.5.2.7 Verify each ECCS throttle valve listed 18 months below is secured in the correct position.

Unit 1 Valve Number Unit 2 Valve Number 1-SI-188 2-SI-89 1-SI-191 2-SI-97 1-SI-193 2-SI-103 1-SI-203 2-SI-116 I-SI-204 2-SI-111 1-SI-205 2-SI-123 SR 3.5.2.8 Verify, by visual inspection, each ECCS 18 months train containment sump component is not restricted by debris and shows no evidence of structural distress or abnormal corrosion.

North Anna UIitsl I and 2 . J . 9.-

Amendment Nos. 250, 230

Containment Pressure

3.6.4 Ranges

Containment Temperature 86-115F RWST Temperature: 50'F 13.0 12.5 IL S12.0 CL 0

.S E

E 11.0 0

10.5 10.0 35 40 45 50 55 60 65 70 75 so 85 90 95 100 Service Water Temperature (F)

Figure 3.6.4-1 (page 1 of 1)

Containment Air Partial Pressure Versus Service Water Temperature giJ III AI II L iu C 0

-j .

C u

• A _')

Amendment Nos. 250, 230

Containment Air Temperature 3.6.5 3.6 CONTAINMENT SYSTEMS 3.6.5 Containment Air Temperature LCO 3.6.5 Containment average air temperature sha 11 be Ž 86°F and 5 115 0 F. I APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment average A.1 Restore containment 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> air temperature not average air within limits, temperature to within limits.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5.1 Verify containment average air temperature 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is within limits.

kiIULIJlio UIIL Lc~U C 3...c. 5-1 Amendment Nos. 250, 230

RS System 3.6.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY I

SR 3.6.7.6 Verify on an actual or simulated actuation 18 months signal(s):

a. Each RS automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position;

b. Each RS pump starts automatically; and

c. Each casing cooling pump starts automatically.

SR 3.6.7.7 Verify, by visual inspection, each RS train 18 months containment sump component is not restricted by debris and shows no evidence of structural distress or abnormal corrosion.

SR 3.6.7.8 Verify each spray nozzle is unobstructed. Following maintenance I

which could cause nozzle blockage North Anna Units 1 and 2 1.9.7-q Amendment Nos. 250, 230

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 Safety Function Determination Program (SFDP) (continued) analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:

a. A required system redundant to the system(s) supported by the inoperable support system is also inoperable; or

b. A required system redundant to the system(s) in turn supported by the inoperable supported system is also inoperable; or

c. A required system redundant to the support system(s) for the supported systems (a) and (b) above is also inoperable.

The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist ,by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.

5.5.15 Containment Leakage Rate Testing Program

a. A program shall establish 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 as modified by the following exception:

NEI 94-01-1995, Section 9.2.3: The first Unit 1 Type A test performed after the April 3, 1993 Type A test shall be performed no later than April 2, 2008.

b. The calculated peak containment internal pressure for the design basis loss of coolant accident, Pas is 42.7 psig. The containment design pressure is 45 psig.

c. The maximum allowable containment leakage rate, La, at Pas shall be 0.1% of containment air weight per day.

(continued)

North Anna Units 1 and 2 5.5-14 Amendment Nos. 250, 230