Text

Amends 87 & 60 to Licenses DPR-70 & DPR-75,respectively, Modifying Reactor Coolant Pump Breaker Position Trip Logic
	ML20207D211
Person / Time
Site:	Salem
Issue date:	08/08/1988
From:	Butler W; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20207D214	List: ML20207D211; ML20207D223;
References
	NUDOCS 8808150291
	Download: ML20207D211 (14)
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UNITED STATES 8

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PUBLIC SERVICE ELFCTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELPARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-372 sal.EM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILIT'Y OPERATING LICENSE Amendment No. 87 License No. DPR-70 1.

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

A.

The application for amendment filed by the Public Service Electric &

Gas Company, Philadelphia Electric Company,(Delmarva Power and Light Company ar.d Atlantic City Electric Company the licensees) dated Ju'iy 24, 1987 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and +he Comission's rules and ragulations 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)thattheactivitiesauthorizedby this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compilance with the Comission's regulations set forth in 10 CFR Chapter I; D.

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

The issuance of this amendment is in accordance with 10 CFR Part 51 of l

the Comission's regulations and all applicable requirements have been i

satisfied.

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l 2.

Accordingly, the license is amended by changes to the Technical Specifica-l tions as indicated in the attachment to this license amendment, and I

paragraph 2.C.-(2) of Facility Operating License No. CPR-70 is hereby i

amended to read as follows:

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,. (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 87, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effectivt as of the next refueling outage, cycle 8, currently sheduled for April 1989.

FOR THE NUCLEAR REGULATORY COMISSION Donald C. Fischer for Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects 1/II

Attachment:

Changes to the Technical Specifications Date of f.ssuance: August 8, 1988

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, (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

87, are hereby incorporated in the license.

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

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This license amendment is effective as of the next re#ueling outage, cycle 8, currently sheduled for April 1989.

FOR THE NUCLEAR REGULATORY COMMISSION

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Walter R. Butler, Director Project Directceate I-2 Division of Reactor Projects I/II

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 8, 1988 n

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ATTACHMENT TO LICENSE AMENDMENT NO. a7 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:

Remove Pages Insert Pages B 2-8 8 2-8 3/4 3-4 3/4 3-4 3/4 3-7 3/4 3-7 0

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LIMITING SAFETY SYSTEM SETTINGS BASES Safety injection Input from ESF If a reactor trip has not already been genereted by the reactor protective instru:nentation, 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 Trip is an anticipatory trip which provides reactor core protection against DNB resulting from the opening of two or more pump breakers above P-7.

This trip is blocked below P-7.

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

SALEM - UNIT 1 B 2-8 Amendment No. 87

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TAB LE 3.3-1 (Continued) z

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REACTOR TRIP SYSTEM INSTRLMENTATION MINIMUM TOTAL NO.

CHANNELS CfiANNE LS APP LICAB LE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERAB LE MO0ES ACTION

18. Turbine Trip a.

Low Autostop 011 Pressure 3

2 2

1 7s b.

Turbine Stop Valve Closure 4

4 3

I 6#

l

19. Safety Injection Input from SSPS 2

1 2

1,2 1

20. Reactor Coolant Pump Breaker 1/ breaker 2

1/ breaker i

11 Position Trip (above P-7) per oper-w

}

ating loop

21. Reactor Trip Breakers 2

1 2

1,2 and* l###

22. Automatic Trip Logic 2

1 2

1,2 and* 1

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TAB E 3.3-1 (Continued) l ACTION 9 - With a channel associated with an operating loop inoperable, restore i

the inoperable channel to OPERABE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in HOT STANWY 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 cperating 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.

ACTION 10 - Deleted ACTI0t.11 - With less than the Minimum Number of Channels OPERABE, 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 chancels OPERABE one less than required by the l

Minimum Channels OPERABE requirement, restore the inoperable channel to OPERABE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANmY 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.

REACTOR TRIP SYSTEM INTERLOCKS ES IGNATION CON 0! TION AND SETPOINT FUNCTION P-6 With 2 of 2 Intermediate Range P-6 prevents or defeats l

Neutron Flux Channels < 6 x 10-11 the manual block of source arrp s,

range reactor trip.

P-7 With 2 of 4 Power Range Neutron P-7 prevents or defeats the Flux Channels > 11% of RATED autom$ tic block of reactor THERNAL POWER or 1 of 2 Turbine trip on:

Low flow in more impulse chamber pressure channels than one primary coolant

> a pressure equivalent to 11% of loop, reactor coolant pump TATED THERMAL POWER.

undervoltage and under-fraquency, pressurizer low pressure, pressurizer high level, and the opening of more than one reactor coolant pump breaker.

SA EM - UNIT 1 3/4 3-7 Armndment No. 87

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o UNITED STATES l'

','n NUCLEAR REGULATORY COMMISSION t

WASHINGTON, D. C. 20555 s

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PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 AMENDMENT TC FACILITY OPERATING LICENSE Amendment No. 60 License No. DPR-75 1.

The Nuclear Regulatory Comission (the Commission or the NRC) has found that A.

The application for amendment filed by the Public Service Electric &

Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated July 24, 1987 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 confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance: (1) thet 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 set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the comon 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 Si of the Comission's reculations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendnient, and paragraph 2.C.(?) of Facility Operating License No. DPR-75 is hereby amended to read as follows:

3

. (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, at revised through Amendment No. 60, 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 next refueling outage, cycle 4, currently schec'uled for September 1988.

FOR THE NUCLEAR REGULATORY COMMISSION Donald C. Fischer for Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II

Attachment:

Changes to the Technical Specifications Date of Issuance: August 8, 1988

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,; (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 60

, 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 next refueling outage, cycle 4, currently scheduled for September 1988.

FOR THE NUCLEAR REGULATORY COMMISSION

/

O%h, J o c.

Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II

Attachment:

Changes to the Technical Specifications Cate of Issuanc0: August 8, 1988

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ATTACHMENT TO LICENSE AMENDMENT NO. 60 i

FACII.ITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:

Remove Pages Insert Paget B 2-7 8 2-7 3/4 3-4 3/4 3-4 3/4 3-7 3/4 3-7 4

4 1

1 4

, -,, - - -., - - -,..,, -. = _. -,,. -,

LIMITIilG SAFETY SYSTEM SETTINGS

.1 BASES Undervoltage and Underfrequency - Reactor Coolant Pump Busses The Undervoltage and Underfrequency Reactor Coolant Pug bus trips provide l

reactor core protection against OPS 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 puq bus circuit breakers shall not exceed 0.9 seconds.

For underf requency, the delay is set so that the time required for a signal to l

reach the reactor trip breakers after the underfrequency trip set point is reached shall not exceed 0.3 seconds.

Turbine Trip A Turbine Trip causes a direct reactor trip when operating above P-9.

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 Protection 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. M.

Reactor Coolant ? ump Breaker Position Trip The Reactor Coolant Pump Breaker Position Trip is an anticipatory trip which provides reactor core protection against INS resulting from the opening of two or more pump breakers above P-7.

This trip is blocked below P-7.

The open/close position trip assures a reactor trip signal is generated before the lou flow trip set point is reached. No credit was taken in the accident analyses for operation of this trip. The functional capability at the open/close pr.ition settings is required to enhance the overall reliability of the Reactor Protection system.

SALEM - UNIT 2 R 2-7 Amendment No. 60

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TAB LE 3.3-1 (Continued) c-

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REACTOR TRIP SYSTEM INSTRLMENTATION w

MINIM 0M TOTAL NO.

CHANNE LS CHANNE LS APPLICAB LE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERA 8 LE M00ES ACTION

18. Turbine Trip a.

Low Autostop 011 Pressure 3

2 2

1 7#

b.

Turbine Stop Valve Closure 4

4 4

1 7#

[

19. Safety Injection Input from SSPS 2

1 2

1,2 1

s

20. Reactor Coolant Pump Breaker 1/ breaker 2

1/ breaker 1

11 Position Trip (above P-7) per oper-w 1

ating loop

21. Reactor Trip Breakers 2

1 2

1,2 and

l###

W

22. Automatic Trip Logic 2

1 2

1,2 and

1 g

8 t

a 5

8 e

i TAB E 3.3-1 (Continued) l l

ACTION 9 - With a channel associated with an operating loop inoperable, restore l

the inoperable channel to OPERABE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in HOT STAN2Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel assoctited 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.

ACTION 10.. Deleted ACTION 11 With less than the Minimum Number of Channels OPERABE, operation I

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 OPERABE one less than required by the l

Minimum Channels OPERABE requirefrent, restore the inoperable channel to OPERABE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STAN2Y 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.

REACTOR TRIP SYSTEM INTER LOCKS ESIGNATION CONDITION AND SETPCINT FUNCTION P-6 With 2 of 2 Inteimdiate Range P-6 prevents or defeats l

Neutron Flux Channels < 6 x 10-11 the manual block of source arrp s.

range reactor trip.

P-7 With 2 of 4 Power Range Neutron P-7 prevents or defeats the Flux Channels > lit of RATED autoinatic block of reactor THERMAL POWER or 1 of 2 Turbine trip on:

Low flow in more impulse chamber pressure channels than one primary coolant

> a pressure equivalent to 11% of loop, reactor coolant pump TATED THERMAL POWER.

undervoltage and under-frequency, pressurizer low pressure, pressurizer high level, and the opening of more than one reactor coolant pump breaker.

SALEM - UNIT 2 3/4 3-7 Amendment No.60

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