ML20070R918

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Amends 182 & 163 to Licenses NPF-4 & NPF-7,respectively, Revising Surveillance Frequency of Nozzles in Quench Spray & Recirculation Spray Sys from 5 to 10 Yrs
ML20070R918
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 05/16/1994
From: Berkow H
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20070R920 List:
References
NUDOCS 9405230133
Download: ML20070R918 (11)
v • d • e


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UNITED STATES i 'l l E

NUCLEAR REGULATORY COMMISSION ifh' 21 [

WASHINGTON, D.C. 20665-0001

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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE j

DOCKET NO. 50-338 NORTH ANNA POWER STATION. UNIT NO. 1 AMENDMENT TO FACIli11 OPERATING LICENSE Amendment No.182 License No. NPF-4 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated February 25, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the l

Comission; l

C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; l

D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and i

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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l 9405230133 940516 l

PDR ADOCK 05000338 P

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F 2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.D.(2) of Facility Operating License No. NPF-4 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 182, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION Herbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: May 16, 1994 l

1

ATTACHMENT TO LICENSE AMENDMENT N0. 182 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

Remove Paaes Insert Paaes 3/4 6-11 3/4'6-11 3/4 6-12a 3/4 6-12a i

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CCNTANAFET SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.

At least once per 10 years by performing an air or srnoke flow test through each spray l

header and verifying each spray nozzle is unobstructed.

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NORTH ANNA - UNIT 1 3/4 6-11 Amendment No. 182

CONTAlffAENT SYSTEMS CONTAINMENT RECIRCUI.ATION SPRAY SYSTEM SURVEILLANCE REQUIREMENTS 4.6.2.2.1 Each containment recirculation spray subsystem and casing cooling subsystem shall be demonstrated OPERABLE:

At least once per 31 days by verifying that each valve (manual, power operated a.

or automatic) in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position.

b.

Verifying, that on recirculation flow, each outside recirculation spray pump develops a discharge pressure of a 115 psig and each casing cooling pump develops a discharge pressure of a 58 psig when tested pursuant to Specification 4.0.5.

c.

At least once per 18 months by:

\\

1.

Verifying that on a Containment Pressure - High-High signal, each casing cooling pump starts automatically without time delay, and each j

recirculation spray pump starts automatically with the following time delays: inside 195 i 9.75 seconds, outside 210121 seconds.

2.

Verifying that each automatic valve in the flow path actuates to its correct l position on a containment pressure high-high test signal, d.

At least once per 10 years by performing an air or smoke flow test through each l

spray header and verifying each spray nozzle is unobstructed.

4.6.2.2.2 The casing cooling tank shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

1.

Verifying the contained borated water volume in the tank, and 2.

Verifying the boron concentration of the water.

b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the casing cooling tank temperature.

NORTH ANNA UNIT - 1 3/4 6-12a Amendment No. 4,182

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UNITED STATES E 'I W B

NUCLEAR REGULATORY COMMISSION "E

WASHINGTON. D.C. 20555-0001

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s, s VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 163 License No. NPF-7 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated February 25, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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. 'l 2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment.to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 163, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR T E NUCLEAR REGULATORY COMMISSION i

H bert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: May 16, 1994

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ATTACHMENT'T0 LICENSE AMENDMENT NO. 163 10 FACILITY OPERATING LICENSE N0. NPF-7 DOCKET NO. 50-339 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment-number and contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness.

Remove Paaes Insert Paaes 3/4 6-10 3/4 6-10 3/4 6-12 3/4 6-12

.. -. - -. -.. -. - -... - -. =

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CONTAINMENT SYSTEMS t

CONTAINMENT STRUCTURAL INTEGRITY LIMITING CONDITIONS FOR OPERATION l

3. 6.1. 6 The structural integrity of the containment shall be maintained at-a level consistent with the acceptance criteria in Specification 4.6.1.6.1.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the structural. integrity of the containment not conforming to the above requirements, restore the structural integrity to within the-limits within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />scr be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.1.6.1 Containment Surfaces The structural-integrity of the exposed accessible interior and exterior surfaces of the containment, including the liner plate, shall be determined during the shutdown for each Type A contain-ment leakage rate test (reference Specification 4.6.1.2)-by r. visual inspec-tion of these surfaces. This inspection shall be performed prior to the f

Type A containment leakage rate test to verify no apparent changes in-i appearance or other abnormal degradation.

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4. 6.1. 6. 2 Reports Any abnormal degradation of the containment structure detected during the above required tests and inspections shall be reported l

to the Commission pursuant to Specification 6.9.2.

This report shall include j'

i a description of the condition of the concrete and liner, the inspection procedure, the tolerances on cracking, and the corrective actions taken.

NORTfl ANNA -- UNIT 2 3/4 6-9 Amendment No. 47

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CCNTAltWENT SYSTEMS 3rd.6.2 DEPRESSURIZATION AND COOLING SYSTEMS f

CONTAINMENTQUENCH SPRAY SYSTEM i

f UMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment quench spray subsystems shall be OPERABLE.

APPLICABILITY: MODES 1,2,3 and 4.

ACTION:

With one containment quench spray subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.2.1 Each containment quench spray subsystem shall be demonstrated OPERABLE:

a.

At least once per 31 days by:

Verifying that each valve (manual, power operated or automatic) in the 1.

flow path that is not locked, sealed or otherwise secured in position, is in its correct position.

2.

Verifying the temperature of the borated water in it.e refueling water storage tank is within the limits shown on Figure 3.61.

Verifying that on recirculation flow, each pump develops a discharge pressure of b.

greater than or equal to 123 psig when tested pursuant to Specification 4.0.5.

At least once per 18 months during shutdown, by:

c.

Verifying that each automatic vaive in the flow path actuated to its correct 1.

position on a Containment Pressure high-high signal.

Verifying that each spray pump starts automatically on a Containment 2.

Pressure high high signal, At least once per 10 years by performing an air or smoke flow test through each l d.

spray header and verifying each spray nozzle is unobstructed.

Amendment No.163 NORTH ANNA UNIT 2 3/4610

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CONTAINMENT SYSTEMS CONTAINMENT RECIRCUl.ATION SPRAY SYSTEM j

SURVEILLANCE REQUIREMENTS (Continued) i j

b.

Verifying, that on recirculation flow, each outside recirculation spray pump l

develops a discharge pressure of greater than or equal to 115 psig and each casing cooling pump develops a discharge pressure of greater than or equal to 46 a

j psig when tested pursuant to Specification 4.0.5.

i c.

At least once per 18 months by:

1.

Verifying that on a Containment Pressure - High High signal, each

]

casing cooling pumps starts automatically without time delay, and each i

recirculation spray pump starts automatically with the following time delays: Inside 19519.75 seconds, outside 210121 seconds.

i 2.

Verifying that each automatic valve in the flow path actuates to its correct l position on a Containment Pressure -- high high test signal.

d.

At least once per 10 years by performing an air or smoke flow test through each l

spray header and verifying each spray nozzle is unobstructed.

]

4.6.2.2.2 The casing cooling tank shall be demonstrated OPERABLE:

I a.

At least once per 7 days by:

1.

Verifying the contained borated water volume in the tank, and 2.

Verifying the boron concentration of the water.

4 b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the casing cooling tank temperature.

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NORTH ANNA UNIT 2 3/4 6-12 Amendment No.163 2

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