Text

Amend 9 to License NPF-6 Revising Tech Specs Re Limiting Safety Sys Settings,Limiting Condition for Operation & Surveillance Requirements
	ML19273B294
Person / Time
Site:	Arkansas Nuclear
Issue date:	03/19/1979
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Arkansas Power & Light Co
Shared Package
ML19273B296	List: ML19273B294; ML19273B297; ML19273B300;
References
	NPF-06-A-009 NUDOCS 7904060092
	Download: ML19273B294 (9)
	v • d • e

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UNITED STATES NUCLEAR REGULATORY COMMISSION

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ARKAliSAS PO'nER AND LIGHT COMPANY DOCKET No. 50-368 ARKANSAS NUCLEAR ONE, UNIT 2 FACILITY OPERATING LICENSE Amendment No. 9 License No. NFF-6 1.

The Nuclear Regulatory Comaission (the Cctnission) having found that:

A.

The issuance of this license amendment conplies with the standards and requirements of the Atomic Energy Act of 1954, ds amended (the Act), and the Comnission's regulations set forth in 10 CFR Chapter I; B.

The far lity will operate in conformity with the application, as the provisions of the Act, and the 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 regulations of the Conmission's regul at ions ;

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.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and by amending Section 2.C.(2) of Facility Operating License No. NPF-6 as follows:

2.C.(2) Technical Specifications The Technical Specifications contained in Appendices A & B, as revised through Amendment No. 9 are hereby incorporated in license NPF-6.

Arkansas Power and Light Company shall operate the facility in accordance with the Technical Specifications except for the following specific exemption.

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2-The licensee shall be exempted f rom ccmpliance with the following Appendix A Technical Specification related to the steam generator low water level trip setpoint while conducting the stean generator feedwater system waterhancer testing during the initial startup and power ascension testing program.

The value of the steam generator low water level trip setpoint in Item 8(b) of Technical Specification Table 3.3 4 may be reduced, during this testing only, from a value of greater than or equal to 46.5 percent to greater than or equal to 10.0 percent.

3.

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

JOR THE NUCLEAR REGULATORY CCPMISSION o

IJohn F. Stolz, Chief Yight Water Re3ctors Branch No. 1 Division of Project Management Attachment :

Changes to the Technical Specifications Date of Issuance:

pp, ; ;pg

ATTACHMENT 1 TO LICENSE APENDPENT NO. 9 FACILITY OPERATING LICENSE NO. NPF 6 DOCKET NO. 50-368 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. Revised pages are identified by Anendment number and contain vertical lines indicating the area of change.

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

Pages 2-4 3/4 3-18 3/4 6-7

SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.2 LIMITING SAFETY SYSTEM SETTINGS REACTOR TRIP SETPOINTS 2.2.1 The reactor protective instrumentation setpoints shall be set consistent with the Trip Setpoint values shown in Table 2.2-1.

APPLICABILITY: As shown for each channel in Taole 3.3-1.

ACTION:

With a reactor protective instrumentation setpoint less conservative than tne value shown in the Allowable Values column of Table 2.2-1, declare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3.1.1 until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

ARKANSAS - UNIT 2 2-3

E TABLE 2.2-1 c5 REACTOR PROTECTIVE INSTRUMENTAT10ft TRIP SETPOINT LIMITS U

FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES c-5 l.

Manual Reactor Trip Not Applicable Not Applicable

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2.

Linear Power Level - High a.

Four Reactor Coolant Pumps

< 123% of RATED TitERMAL POWER 123.712% of RATED TilERMAL POWER Operating b.

Three Reactor Coolant Pumps Operating c.

Two Reactor Coolant Pumps Operating - Same Loop d.

Two Reactor Coolant Pumps ru b

Operating - Opposite Loops 3.

Logarithmic Power Level -

High (1)

< 0.75% of RATED TliERMAL POWER 1 0.8191 of RATED TliERMAL POWER 4.

Pressurizer Pressure - High

< 2345 psia

< 2353.887 psia F

5.

Pressurizer Pressure - Low

> 1740 psia (2)

> 1686.75 psia (2)

S 6.

Containment Pressure - liigh

< 18.4 psia

< 19.024 psia 7.

Steam Generator Pressure - Low

> 728 psia (3)

> 706.6 psia (3) 5 k

8.

Steam Generator Level - Low

> 46.5% (4)

> 45.611 (4) l

These values lef t blank pending NRC approval of ECCS analyses for operation with less than f our reactor coolant pumps operating.

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i 146; _ ___lt:0 to 80 70 00 90 100 110 120 130 CONTAINedf NT AVERAGE Aan TitsPt4 ATURE

'8 F= pere 161 C esseuronel Premere et Cameanseuset Average Aar Turneursture.

ARKANSAS-UNIT 2 3/46-7 Amendment No. 9

CONTAINMENT SYSTEMS CONTAINMENT STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.5 The structural integrity of the containment shall be miintained at a level consistent with the acceptance criteria in Specification 4.6.1.5.

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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REOUIREMENTS 4.6.1.5.1 Containment Tendons The containment tendons ' structural integrity shall be demonstrated at the end of one, three and five years following the initial containment structural integrity test and at five year intervals thereafter. The tendons' structural integrity shall be demonstrated by a visual examination (to the extent practical and with-out dismantling load bearing components of the anchorage) of a repre-sentative sample

of at least 21 tendon dome, 5 vertical, and 10 hoop) ard verifying no abnormal degradation. Unless there is evidence of abnormal degradation of the containment tendons during the first three tests of the tendons, the number of tendons examined during sub-sequent tests may be reduced to a representative sample of at least 9 tendons (3 dome, 3 vertical and 3 hoop).

For each inspection, the tendons shall be selected on a random but representative basis so that the sample group will change somewhat for each inspection; however, to develop a history of tendon performance and to correlate the observed data, one tendon from each group (dome, vertical, and hoop) may be kept unchanged after the initial selection.

ARKANSAS-UNIT 2 3/4 6-8

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES U

ALLOWABLE f

FUNCTIONAL UNIT TRIP VALUE VALUES E

4.

MAIN STEAM AND FEEDWATER ISOLATION (MSIS) a.

Manual (Trip Buttons)

Not Applicable Not Applicable b.

Steam Generator Pressure - Low 1 728 psia (2) f_ 706.6 psia (2) 5.

CONTAINMENT COOLING (CCAS) a.

Manual (Trip Buttons)

Not Applicaole Not Applicable b.

Containment Pressure - High

< 18.4 psia 19.024 psia c.

Pressurizer Pressure - Low g 1740 psia (1) c 1686.75 psia (1)

R 6.

RECIRCULATION (RAS) a.

Manual (Trip Buttons)

Not Applicable Not Applicable

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Refueling Water Tank - Low 54,400 1 2,370 gallons between 51,050 and 58,600 (equivalent to 6.0 + 0.5%

gallons (equivalent to indicated level) between 5.300% and 6.886%

indicated level) 7.

LOSS OF POWER a.

4.16 kv Emergency Bus Undervoltage (Loss of Voltage) 3120 volts (4) 3120 volts (4) b.

460 volt Emergency Bus Undervoltage 423 + 2.0 volts 423 + 4.0 volts (Degraded Voltage) with an 8.0 1 0.5 with an 8.0 + 0.8 second time delay second time delay

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TABLE 3.3-4 (Continuedl ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES ALLOWABLE SE FL'NCTIONAL UNIT TRIP VALUE VALUES Z

8 EMERGENCY FEEDWATER (EFAS) m a.

Manual (Trip Buttons)

Not Applicable Not Applicable b.

Steam Generator (A&B) Level-Low

> 46.5% (3)

> 45.61% (3) l c.

Steam Generator AP-High (SG-A > SG-B)

< 39 psi s 48.35 psi d.

Steam Generator AP-High (SG-B > SG-A) 1 39 psi 1 48.35 psi e.

Steam Generator (A&B) Pressure - Low

> 728 psia (2) 706.6 psia (2)

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[1) Vilue may be decreased manually, to a minimum of > 100 psia, as pressurizer pressure is reduced, provided the margin between the pressurizer pressure and th_is value is maintained at s 200 psi, the setpoint y

shall be increased automatically as pressurizer pressure is increased until flie trip setpoint is reached.

g Trip may be manually bypassed below 400 psia; bypass shall be automatically removed whenever pressurizer pressure is > 500 psia.

(2) Value may be decreased manually as steam generator pressure is reduced,, provided the margin between the steam generator pressure and this value is maintained at < 200 psi; the setpoint shall be increased automatically as steam generator pressure is increased until the trip setpoint is reached.

(3) % of the distance between steam generator upper and lower level instrument nozzles.

h (4) Inverse time relay set value, not a trip value.

The zero voltage trip will occur in 0.75 + 0.075 seconds.

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ML19273B294

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