Text

Amend 34 to License NPF-12,changing Tech Specs to Allow Installation of P-9 Interlock to Prevent Direct Reactor Trip Following Turbine Trip at or Below 50% Reactor Power
	ML20100N104
Person / Time
Site:	Summer
Issue date:	11/30/1984
From:	Adensam E; Office of Nuclear Reactor Regulation
To:	;
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ML20100N108	List: ML20100N104; ML20100N124;
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	NUDOCS 8412120577
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UNITED STATES g[2 '

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NUCLEAR REGULATORY COMMISSION Jt& ;%.

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SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.34 License No. NPF-12 W'

1.

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

s A.

The application for amendment to the Virgil C. Summer Nuclear Station, Unit No. 1 (the facility) Facility Operating License No. NPF-12 filed by the South Carolina Electric & Gas Company acting for itself and South Carolina Public Service Authority (the licensees), dated May 23, 1984, and supplemented November 27, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission; 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 (11) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.

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

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

7 2.

Accordingly, the license is hereby amended to page changes to the Technical J

Specifications as indicated in the attachments to this ifcense amendment and paragraph 2.C(2) of Facility Operating License No. NPF-12 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amen'dment No. 34, are hereby incorporated into this license.

South Carolina Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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8412120577 841130

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PDR.ADOCK 05000395 P

PDR

2-3.

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

FOR THE NUCLEAR REGULATORY COMMISS!0N EM Elinor G. Adensam, Chief Licensing Branch No. 4 Division'of Licensing

Enclosure:

Technical Specification Change

- Date of Issuance:

November 30, 1984 1

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.f 'MP-ATTACHMENT TO LICENSE AMENDMENT NO. 34 FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by Amendment numbc. and contain vertical lines indicating the areas of change. Corresponding overleaf pages are also provided to maintain document completeness.

Amended Overleaf Pages Pages 2-7 82-7 i

82-8 3/4 3-5 3/4 3-6 3/4 3-13 3/4 3-14 e

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E TABLE 2.2-1 (continued) 49 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS c

Total

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Functional Unit Allowance (TA)

Z S

Trip Setpoint Allowable Value 18.

Safety Injection Input NA NA NA NA NA from ESF 19.

Reactor Trip System Interlocks A.

Intermediate Range NA NA NA 11 x 10 10 amps 16 x 10 11 amps Neutron Flux, P-6 B.

Low Power Reactor Trips Block, P-7 a.

P-10 input 7.5 4.56 0

$10% of RTP

$12.2% of RTP b.

P-13 input 7.5 4.56 0

<10% turbine

<12.2% of turbine Impulse pressure Impulse pressure equivalent equivalent C.

Power Range Neutron 7.5 4.56 0

138% of RTP 140.2% of RTP Flux P-8 D.

Low Setpoint Power 7.5 4.56 0

110% of RTP 17.8% of RTP Range Neutron Flux, P-10

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E.

Turbine Impulse Chamber 7.5 4.56 0

<10% turbine

<12.2% turbine Pressure, P-13 Impulse pressure pressure equivalent y

equivalent E

F.

Power Range Neutron 7.5 4.56 0

150% of RTP 152.2% of RTP l

Flux, P-9 e

20.

Reactor Trip Breakers NA NA NA NA NA Y

21.

Automatic Actuation Logic NA NA NA NA NA RTP = RATED THERMAL POWER

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LIMITING SAFETY SYSTEM SETTINGS

.w BASES Sten /Feedwater Flow Mismatch and Low Steam Generator Water Level (Continued)

I level setpoint, as indicated by the narrow range instrument.

These trip l

values include sufficient allowance in excess of normal operating values to preclude spurious t 'ps but will 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.

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~Undervoltage and Underfrequency - Reactor Coolant Pump Busses The Undervoltage and Underfrequency Reactor Coolant Pump Bus trips provide reactor core protection against DNB as a result of complete loss of forced l

coolant flow.

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 l

following the simultaneous trip of two or more reactor coolant pump bus circuit breakers shall not exceed 1.2 seconds.

For underfrequency, the delay is set so that the time required for a signal to reach the reactor trip breakers after the underfrequency trip set point is reached shall not exceed 0.6 seconds.

On decreasing power the Undervoltage and Underfrequency Reactor Coolant Pump Bus l

trips are automatically blocked by P-7 (a power level of approximately '10 per-l cent of RATED THERMAL POWER with a turbine impulse chamber pressure at approximately 10 percent of full power equivalent-); and on increasing power, reinstated automatically by P-7.

Turbine Trip A Turbine Trip initiates a reactor trip.

On decreasing power, the reactor trip.from the turbine trip is automatically blocked by P-9 (a power level less than or equal to 50% of RATED THERMAL POWER); and on increasing power, reinstated automatically by P-9.

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 j

reactor trip upon any signal which initiates a safety injection.

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

l LUMMER - UNIT 1 B 2-7 Amendment No. 34

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f LIMITING SAFET'Y SYSTEM SETTINGS BASES Reactor Trip System Interlocks The Reactor Trip System Interlocks perform the following functions:

P-6 On increasing power P-6 allows the manual block of the Source Range reactor trip and de energizing of the high voltage to the detectors.

On decreasing power, Source Range level trips are automatically reactivated and high voltage restored.

P-7 On increasing power P-7 automatically enables reactor trips on low flow in more than one primary coolant loop, more than one reactor coolant pump breaker open, reactor coolant pump bus undervoltage and underfrequency, turbine trip, pressurizer. low pressure and pressurizer high level.

On decreasing power the above listed trips are automati-cally blocked.

P-8 On increasing power P-8 automatically enables reactor trips on low flow in one or more primary coolant loops, and one or more reactor coolant pump breakers open.

On decreasing power the P-8 automatically.

blocks the above listed trips.

P-9 On increasing power P-9 automatically e.nables reactor trip on turbine trip.

On decreasing power P-9 automati,cally blocks reactor trip on turbine trip.

i l'

P-10 On increasing power P-10 allows the manual block of the Intermediate Range reactor trip and the low setpoint Power Range reactor' trip; and automatically blocks the Source Range reactor trip and de-energizes the Source Range high voltage power.

On decreasing power the Inter-mediate Range reactor trip and the low setpoint Power Range reactor trip are automatically reactivated.

Provides input to P-7.

P-13 Provides input to P-7.

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f SUMMER - UNIT 1 8 2-8 Amendment No. 34

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E TABLE 3.3-1 (Continued) t 5

2 REACTOR TRIP SYSTEM INSTRUMENTATION i

c MINIMUM

' i'i TOTAL NO.

CHANNELS CHANNELS APPLICABLE

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FUNCTIONAL UNIT OF CHANNELS.

TO TRIP OPERABLE MODES ACTION 19.

Reactor Trip System Interlocks 1

A.

Intermediate Range Neutron Flux, P-6 2

1 2

2, 7

t B.

Low Power Reactor j

Trips Block, P-7 P-10 Input 4 2

3 1

7 P-13 Input 2 1

2 1

7 C.

Power Range Neutron Flux, P-8 4

2 3

1 7

N 0.

Power Range Neutron Y

Flux, P-10 4

2 3

1, 2 -

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Turbine First Stage-j Pressure, P-13 2

1 2

1 7

F.

Power Range Neutron Flux, P-9 4

2

.3 1

7 1

1 20.

Reactor Trip Breakers 2

1 2

1, 2 8

2 1

2 3*, 4*, 5*

9 21.

Automatic Trip Logic 2

1 2

1, 2 8

2 1

2 3*, 4*,-5*

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TABLE NOTATION With the reactor trip system breakers in the. closed position and the control rod drive system capable of rod withdrawal.

The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped

' condition.

The provisions of Specification 3.0.4 are not applicable.

1. Below the P-6 (Intermediate Range Neutron Flux Interlock) setpoint.

1. 1. elow the-P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

B

- - - Values left blank pending NRC approval of E loop operation.

i ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than 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 at least HOT STAND 8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provirled the following conditions-are satisfied:

l a.

The inoperable channel is placed in the tripped condition l

within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .'

i b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel 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 of other channels per Specification 4.3.1.1.

c.

Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux trip setpoint is reduced to less than or equal to l-85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per Specification 4.2.4.2.

SUMMER - UNIT 1 3/4 3 6 i

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TABLE 4.3-1 (Continued)

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REACTOR' TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS

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TRIP ANALOG ACTUATING MODES FOR CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE 4

i FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED D.

Low Setpoint Power Range Neutron Flux, P-10 N.A.

R(4)

M (8)

N. i.

N.A.

1, 2 E.

Turbine Impulse Chamber Pressure, P-13 N.A.

R M (8)

N.A.

1 F.

Low Power Range Neutron Flux, P-9 N.A.

R(4)

M (8)

N.A.

1 20.

Reactor Trip Breaker N.A.

N.A.

M (7, 11)

N.A.

1, 2, 3*,.4*, 5*

i Y0 21.

Automatic Trip Logic N.A.

N.A.

M (7) 1, 2, 3*, 4*, 5*

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TABLE 4.3-1 (Continued)

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TABLE NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

Below P-6 (Intermediate Range Neutron Flux Interlock) setpoint.

Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) setpoint.

(1)

If not performeci in previous 7 days.

Comparison of calorimetric to excore power indication tbove 15% of (2)

RATED THERMAL POWER.

Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2 percent.

The provisions of Specification 4.0.4 are not. applicable for entry into MODE 2 or 1.

(3)

Single point compcrison of incore to excore axial flux difference above 15% of RATED THERMAL POWER.

Recalibrate if the absolute difference is greater than or equal to 3 percent.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

Neutron detectors may be exclucied from CHANNEL CALIBRATION.

(4)

Detector plateau curves shall be obtained evaluated and compared (5) to manufacturer's data.

FortheIntermedIateRangeand'PowerRange Neutron Flux Channels the )tovisions of Specification 4.0.4 aFe not applicable for entry into A0DE 2 or 1.

Incore - Excore Calibration, above 75% of RATED THERMAL POWER.

The (6) provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

Each train shall be tested at least every 62 days on a STAGGERED TEST (7)

BASIS.

With power greater than or equal to the interlock setpoint the required (8)

OPERATIONAL TEST shall consist of verifying that the interlock is in the required state by observing the permissive annunciator window.

Monthly Surveillance in MODES 3*, 4* and 5* shall also include (9) verification that permissives P-6 and P-10 are in their required l

state for existing plant conditions by observation of the permissive l

annunciator window.

(10)-

Setpoint verification is not required.

(11)-

Atleastonceper18monthsandfollowingmaintenanceoradjustment of the reactor trip breakers, the TRIP ACTUATING DEVICE OPERATIONAL

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TEST shall include an independent verification of the undervoltage

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and shunt trips.

SUMMER - UNIT 1 3/4 3-14 i

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ML20100N104

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