Text

Amends 119 & 103 to Licenses NPF-4 & NPF-7,respectively, Allowing Direct Reactor Trip on Turbine Trip to Be Blocked Below 30% of Rated Thermal Power
	ML20247H190
Person / Time
Site:	North Anna
Issue date:	07/18/1989
From:	Berkow H; Office of Nuclear Reactor Regulation
To:	;
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References
	NUDOCS 8907280310
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- WAftou q'og UNITED STATES j

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NUCLEAR REGULATORY COMMISSIO.N

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E WASHINGTON, D. C. 20555 VIRGINIA ELECTRIC AND POWER COMPANY OLD 00!! INION ELECTRIC COOPERATIVE.

DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO.- 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 119 License No. NPF-4 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 September 30, 1988, 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 j

the Commission; 1

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 Comission's regulations and all applicable requirements have been satisfied.

8907280310 890718 PDR ADOCK 05000338

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Accordingly, the'11 cense 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:

i (2) Technical' Specifications The Technical Specifications contained in. Appendices A and B, as revised through Amendment No.119, 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 the date of its issuance and shall be implemented no later than the end of the next refueling outage.

FOR THE NUCLEAR REGULAIORY COMMISSION T

{'

Herbert N.

brector project Diree: orate 11 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

July 18, 1989

1 ATTACHMENT TO LICENSE AMENDMENT NO.119 TO FACILITY OPERATING LICENSE '40. 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 nurber and contain vertical lines indicating the area of change.

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

Page B2-7 3/4 3-8 3/4 3-9 1

w-____-__

. W, LIMITING SAFETY SYSTEM SETTINGS BASES of the Reactor Protection System. This trip is redundant to the Steam Generator Water. Level Low-Low trip. The Steam /Feedwater Flow Mismatch portion of this trip is activated when the steam flow exceeds the feedwater flow by > 1.616 x 106 lbs/ hour of full steam flow at RATED THERMAL POWER. The Steam Generator Low Water level portion of the trip is activated when the water level drops below 25 percent, as indicated by the narrow range instrument.. These trip values include sufficient allowance in excess of normal operating values to preclude spurious trips but w411 initiate a reactor trip before the steam generators are dry. Therefore, the required capacity and starting time requirements of the auxiliary feedwater pumps are reduced and the resulting thermal transient on the Reactor Coolant System and steam generators is minimized.

Undervoltage and Underfrequency - Reactor Coolant Pump Busses The reactor trip due to the Undervoltage and Underfrequency on the Reactor Coolant Pump busses provide reactor core protection against DNB as a result of loss of voltage or underfrequency to more than one reactor coolant pump. The specified set points assure a. reactor trip signal is generated before the low flow trip set point is reached. Time delays are incorporated in the underfrequency and undervoltage trips to prevent spurious reactor trips' from momentary electrical power transients.

For undervoltage, the delay is set so that' the time required ~ for a signal to reach the reactor trip breakers following the simultaneous trip of two or more reactor coolant pump bus circuit breakers shall not exceed 0.5 seconds.

For underfrequency, the delay is set so thit the time required for a' signal.to reach the reactor trip breakers after the underfrequency.

trip set point is reached shall not exceed 0.1 seconds.

The undervol-tage and underfrequency trips are automatically blocked when reactor power is below the P-7 setpoint.

Turbine Trip A Turbine Trip causes a direct reactor trip when operating above P-8.

l Each of the turbine trips provide turbine ~ protection and reduce the severity of the ensuing transient. No credit was taken in the accident analyses for operation of these trips. Their functional capability at the specified trip settings is required to enhance tM overall reliability of the Reactor l

Protection System.

NORTH ANNA-UNIT 1 B 2-7 Amendment No. 119

1 1

1 LIMITING SAFETY SYSTEM SETTINGS BASES Safety Injection Input from ESF If a reactor trip has not already been generated by the reactor l

protective instrumentation, the ESF automatic actuation logic channels will initiate a reactor trip upon any signal which initiates a safety injection. This trip is provided to protect the core in the event of a LOCA. The ESF instrumentation channels which initiate a safety injection signal are shown in Table 3.3-3.

Reactor Coolant Pump Breaker Position Trip The Reactor Coolant Pump Breaker Position Trips are anticipatory trips which provide reactor core protection against DNB resulting from the opening of any one pump breaker above P-8 or the opening of two or more pump breakers below P-8.

These' trips are blocked below P-7.

The open/close position trips assure a reactor trip signal is generated before the low flow trip set point is reached. No credit was taken in the accident analyses for operation of these trips. Their functional capability at the open/close position settings is required to enhance the overall reliability of the Reactor Protection System.

NORTH ANNA-UNIT 1 B 2-8

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. TABLE 3.3-1 (Continued)

ACTION 9 -

With'a channel associate'd with an operating loop inoperable, o

restore the inoperable channel to OPERABLE status within L

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel associated with an' operating loop may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveil ~ance testing

.per Specification 4.3.1.1.1.

ACTION 10 -

With' one channel inoperabic, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to below P-8 within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Operation below P-8 may continue pursuant to ACTION 11.

ACTION 11 -

With less than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is nlaced'in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 12 -

With the number of channels OPERABLE one less than re-quired by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 4

and/or open the reactor trip breakers.

ACTION 13 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within (1) hour or terminate testing of the Reactor Trip Breaker and open the Reactor Trip Bypass Breaker.

ACTION 14 -

With one of the diverse trip features (undervoltage or shunt trip device) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply Action 1.

Th'e breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for p;rforming maintenance to restore the breaker to OPERABLE status.

ACTION 15 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the reactor trip breakers within the next hour.

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UNITED STATES '

8-NUCLEAR REGULATORY COMMISS!ON o

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E WASHINGTON, D. C. 20555 '

o 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.103 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 September 30, 1988, 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 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 commen 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.

,, C 4

a 3

I ' g1,

, 2..

Accordingly, the license is amended by changes to the Technical peci-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 Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.103

, are hereby incorporated in the' license.

The licensee shall operate the facility in accordance with the Technical Specifications.-

l 3.

. This license amendment is effective as of the date of its issuance and shall be implemented no later than the end of the next refueling' outage.

FOR THE NUCLEAR REGULATORY COMMISSION 4 ~.

d D

tr HeTbert N. Byko, Director Project Dired. orate 11-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: July 18, 1989 1

i

-l

ATTACHMENT TO LICENSE AMENDMENT NO.103 TO FACILITY OPERATING LICENSE NO. 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.

Page B2-7 3/4 3-8 3/4 3-9 i

4 l

O 4

LIMITING SAFETY SYSTEM SETTINGS BASES Undervoltage and Underfrequency - Reactor Coolant Pump Busses The reactor trip due to the Undervoltage and Underfrequency on the Reactor Coolant Pump Busses provide reactor core protection against DNB as a result of loss of voltage or underfrequency to more than one reactor coolant pump.

The specified set points assure a reactor trip signal is generated before the low flow trip set point is reached.

Time delays are incorporated in the underfre-quency and undervoltage trips to prevent spurious reactor trip; from momentary electrical power transients.

For undervoltage, the delay is set so that'the time required for a signal to reach the reactor trip breakers following the simultaneous trip of'two or more reactor coolant pump bus circuit breakers shall not exceed 0.5 seconds.

For underfrequency, the delay is set so that the time required for a signal to reach the reactor tr'p breakers after the underfrequency trip set point is reached shall not exceed 0.1 seconds." The undervoltage and underfrequency trips are automatically blocked when reactor power is below the P-7 setpoint.

Turbine Trig A Turbine Trip causes a direct reactor trip when operating above P-8.

l Each of the turbine trips provide turbine protection and reduce the severity of the ensuing transient.

No credit was taken in the accident analyses for operation of these trips.

Their functional capability at the specified trip settings is required to enhance the overall reliability of the Reactor Protec-tion System.

Safety Injection Input from ESF If a reactor trip has not already been generated by the reactor protective instrumentation, the ESF automatic actuation logic channels will initiate a reactor trip upon any signal which initiates a safety injection. This trip is provided to protect the core in the event of a LOCA.

The ESF instrumentation channels which initiate a safety injection signal are shown in Table 3.3-3.

Reactor Coolant Pump Breaker Position Trip The Reactor Coolant Pump Breaker Position frips are anticipatory trips which provide reactor core protection against DNB resulting from the opening of any one pump breaker above P-8 or the opening of two or more pump breakers below P-8.

These trips are blocked below P-7.

The open/close position trips assure a reactor trip signal is generated before the low flow trip set point NORTH ANNA - UNIT 2 8 2-7 Amendment No.103

J 1

j i

i J

LIMITING SAFETY SYSTEM SETTINGS I

BASES is reached.

No credit was taken in the accident analyses for operation of these trips.

Their functional capability at the open/close position settings is required to enhance the overall reliability of the Reactor Protection System.

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NORTH ANNA - UNIT 2 8 2-8 l

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l TABLE 3.3-1 (Continued)

L ACTION 9 With a channel associated with an operating loop inoperable, restore the inoperable channel to OPEPABLE status within l

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel associated with an operating loop may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing'per-Specification 4.3.1.1.1.

ACTION 10 - With one channel inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to below the P-8, (Block of Low Reactor Coolant Pump Flow and Reactor Coolant Pump Breaker Position) setpoint, within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Operation below the P-8, (Block of Low Reactor Coolant Pump Flow and Reactor Coolant Pump Breaker Position) setpoint, may continue pursuant to ACTION 11.

ACTION 11 - With less than the tiinimum Number sf Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 12 - With the number of channels OPERABLE one ie>> Inan required by the Minimum Channels OPERABLE requirement, restore the inoperable channel.to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the reactor trip breakers.

ACTION 13~-' With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within (1) hour or terminate testing of the Reactor Trip Breaker and open the Reactor Trip Bypass Breaker.

ACTION 14 - With one of the diverse trip features (undervoltage or shunt trip device) inoperable, restore it to OPERABLE status within 4

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply Action 1.

The breaker shall not be bypassed while-one of the diverse.

trip features is inoperable except for the time required for i

performing maintenance to restore the breaker to OPERABLE status.

ACTION 15 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement restore the inoperable channel.to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the reactor trip breakers within the next hour.

NORTH ANNA - UNIT 2 3/4 3-7 Amendment No.69 i

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