ML20058D637

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Amends 176 & 157 to Licenses NPF-4 & NPF-7,respectively, Revising TS for Surveillance Requirements Re Simulated Reactor Coolant Pump Seal Injection Flow Requirements
ML20058D637
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 11/23/1993
From: Berkow H
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20058D640 List:
References
NUDOCS 9312030240
Download: ML20058D637 (10)
v • d • e


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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENjf Amendment No. 176 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 November 10, 1993, as supplemented by letter dated November 16, 1993, 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 Comission; 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; 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 Comission's regulations and all applicable requirements have been satisfied.

9312030240 931123 PDR ADOCK 05000338 p

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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 Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 176, 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.

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

Attachment:

Changes to the Technical Specifications Date of Issuance: November 23, 1993

s ATTACHMENT T0 LICENSE AMENDMENT NO. 176

+

TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET N0. 50-318 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page as indicated. The revised page is identified by amendment number and contains a vertical line indicating the area of change.

The corresponding overleaf page is also provided to maintain document completeness.

i Remove Paae Insert Paag 3/4 5-5 3/4 5-5 P

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s h

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EMERGCNCYCOR:CCOJG SYSTEM SURVEILLANCE RECUIREMENTS fContinued)

2. Verifying that each of the following pumps start automa' cally upon receipt of a safety injection test signal:

a) Centrifugal charging pump, and b) Low head safety injection pump.

f.

By verifying that each of the following pumps develops the indicated discharge pressure (after subtractinD suction pressure) on recirculation flow when tested pursuant to Specification 4.0.5.

1.

Centrifuga! charging pump 2 2410 psig.

2. Low head safety injection pump 2156 psig.

g.

By verifying that the following manual valves requiring adjustment to prevent pump

" runout" and subsequent component damage are locked and tagged in the proper position for injection:

1. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> followinD completion of any repositioning or maintenance on the valve when ECCS systems are required to be OPERABLE.
2. At least once per 18 months.

1.

1-SI-188 Loop A Cold Leg 2.

1 -SI-191 Loop B Cold Leg 3.

1 SI-193 Loop C Cold Leg 4.

1-SI-203 Loop A Hot Leg 5.

1 -SI-204 Loop B Hot Leg 6.

1-SI 205 Loop C Hot Leg

h. By performing a flow balance test, during shutdown, following completion of modifications to the ECCS subsystems that alter the subsystem flow characteristics and verifying that:

1.

For high head safety injection lines, with a single pump running:

a) The sum of the injection line flow rates, excluding the highest flow rate, is 2 359 gpm, and b) The total pump flow rate is s 660 gpm.

NORTH ANNA-UNIT 1 3/4 5-5 Amendment No4, M, W1, 176

EMERGEPCYCORECOO!fG SYST9AS j

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ECCS SUBSYSTEMS - Tava < 350T i

UMITING CONDITION FOR OPERATION l

3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE.

a. One OPERABLE centrifugal charging pump #,

I

b. One OPERABLE low head safety injection pump #, and c.

An OPERABLE flow path capable of automatically transferring fluid to the reactor coolant system when taking suction from the refueling water storage -

tank or from the containment sump when the suction is transferred during i

the recirculation phase of operation or from the discharge of the outside recirculation spray pump.

t APPLICABILITY:

MODE 4.

ACTICtt 7

a.

With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> t

or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.

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b. With no ECCS subsystem OPERABLE because of the inoperability of the low head safety injection pump, restore at least one ECCS subsystem to OPERABLE status or maintain the Reactor Coolant System Tavg less than 350'F by use of alternate heat removal methods.

c.

In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.

A maximum of one centrifugal charging pump and one low head safety injection pump shall be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or equal to 316*F.

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NORTH ANNA - UNIT 1 3/4 5-6 Amendment No.6,+6,64,4+7,170

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NUCLEAR REGULATORY COMMISSION ggg f

WASHINGTON. D.C. 20555 (Kc1 g xs j 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 I

Amendment No. 157 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 November 10, 1993, as supplemented by letter dated November 16, 1993, 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 i

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.

T f

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i

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

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amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 157, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

i 3.

This license amendment is effective as of its date of issuance.

FOR HE NUCLEAR REGULATORY COMMISSION (Ss jE)is Herbert N. Ber ow, Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications l

Date of Issuance: November 23, 1993 1

i

ATTACHMENT TO LICENSE AMENDMENT NO. 157 l

TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page as indicated.

The revised page is identified by amendment

?

number and contains a vertical line indicating the area of change.

The corresponding overleaf page is also provided to maintain document completeness.

Remove Pace Insert Pace 3/4 5-5 3/4 5-5 i

f i

1 f

4 i

I.

EMERMFCYCORECOOLN3 SYSTEM SURVEILLANCE REQUIREMENTS (Continued) f.

By verifying that each of the following pumps develop the indicated discharge i

pressure (after subtracting suction pressure) on recirculation !!ow when tested pursuant to Specification 4.0.5.

1. Centrifugal charging pump greater than or equal to 2410 psig.
2. Low head safety injection pump greater than or equal to 156 psig.

By verifying that the following manual valves requiring adjustment to prevent pump g.

  • runout' and subsequent component damage are locked and tagged in the proper position for injection:
1. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of any repositioning or maintenance on the vane when the ECCS systems are required to be OPERABLE.
2. At least once per 18 months.

j 1.

2-SI-89 Loop A Cold Leg 2.

2-SI-97 Loop B Cold Leg 3.

2 Sl-103 trop C Cod Leg i

i 4.

2.SI-116 Loop A Hot Leg I

5.

2 SI 111 Loop B Hot Leg 6.

2 SI-123 Loop C Hot Leg h.

By performing a flow balance test, during shutdown, following completion of l

moditications to the ECCS subsystems that alter the subsystem flow characteristics and veritying that; j

1.

For high head safety injection lines, with a single pump running:

a) The sum of the injection line flow rates, excluding the highest flow rate, is 2 359 gpm, and I

b) The total pump ilow rate is s 660 gpm.

NORTH ANNA - UNIT 2 3/4 5-5 Amendment No.M. I57

l BAERGEPCYCORE COOLPf3 SYSTBAS

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ECCS SUBSYSTEMS - Tavo LESS THAN 350*F UMmNG CONDITION FOR OPERATION l

3.5.3 As a minirrum, 'e ECCS subsystem comprised of the following shall be OPERABLE:

a One OPERABLE centrifugal charging pump #,

b. One OPERABLE low head safety injection pump #, and
c. An OPERABLE flow path capable of automatically transferring fluid to the reactor coolant system when taking suction from the refueling water storage tank or from the containment sump when the suction is transferred during the recirculation phase of operation.

APPLICABILITY:

MODE 4.

?

ACTION:

a With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />,

b. With no ECCS subsystem OPERABLE because of the inoperability of the low head safety injection pump, restore at least one ECCS subsystem to OPERABLE status or maintain the Reactor Coolant System Tavg less than 350'F by use of alternate heat removal methods.

l c.

In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The i

current value of the usage factor for each affected safety injection nozzle i

shall be provided in this Special Report whenever its value exceeds 0.70.

A maximum o7one centrifugal charging pump and one low head safety injection pump shall be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or equal to 358'F.

l NORTH ANNA - UNIT 2 3/4 5-6 Amendment No.-74,149

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