ML19261A408

Modifies 781220 Request to Change AR Nuclear One Unit 2 Tech Spec Tables 2.2-1&3.3-4.Changes Involve Low Pressurizer Pressure & Low Steam Generator Pressure Trip Setpoints

ML19261A408
Person / Time
Site:	Arkansas Nuclear
Issue date:	01/09/1979
From:	Cavanaugh W ARKANSAS POWER & LIGHT CO.
To:	Stolz J Office of Nuclear Reactor Regulation
References
2-019-5, 2-19-5, NUDOCS 7901180145
Download: ML19261A408 (5)

Text

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. ARKANSAS POWER & LIGHT COMPANY POST CFFICE BOX 551 LITTLE RCCK. ARKANSAS 72203 (501)371-4422 January 9, 1979 WILLIAM CAVANAUGH lil Executwe Director Generation & Construction 2-019-5 Director of Nuclear Reactor Regulation ATTN: Mr. J. F. Stolz, Chief Light Water Reactor Branch #1 U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Subject:

Arkansas Nuclear One-Unit 2 Docket No. 50-368 License No. NPF-6 Technical Specification Change Request (File: 2-1511.1)

Gentlemen:

Our letter of December 20, 1978, proposed changes to ANO-?

Technical Specification Tables 2.2-1 and 3.3-4. The changes ,

requested involved the low pressurizer pressure and low steam generator pressure trip setpoints. We also pointed out that as a result of ongoing evaluations that we might request a future change to those setpoints.

hvaluations have-been completed which substantiate the set-points that currently exist in the Technical Specifications

(> 1740 psia for the low pressurizer pressure trip setpoint and > 728 psia for the low steam generator pressure setpoint) as applicabic and indeed conservative for use at ANO-2.

These values were originally calcula.ted for the Fischer S Porter (F6P) transmitters which originally performed thcre functions.

Errors associated with the FSP instruments (as a result of environmental qualification) were incorporated into the set-points as margin.

As you know, these FGP transmitters have been replaced with Rosemount transmitters. From our recent environmental quali-fication of the Rosemount transmitters, we fcund that the corresponding Rosemount errors are smaller than the F6P errors.

Therefore, use of the existing setpoints is appropriate and conservative. .

7901180 M Nd5r/BE R MiOOLE '3OUTH UTILIT .5 SY STEM

Director of Nuclear Reactor Regulation January 9, 1979 Page Two We have also replaced the FSP low steam generator level trans-mitters with Rosemount transmitters. Again, the errors associated with the Rosemount transmitters are smaller than those associated with the FSP transmitters. Accordinely, new setpoint calculations using the appropriate Rosemount errors have been performed which iustify a new low steam cenerator level trip setpoint of > 46.5% as opposed to the existing value of > 49.4%. This new value was calculated using the same procedure and methodology as the existing value.

Based on the above, we wish to modify our December 20, 1978, request to change the pressurizer pressure and low steam generator pressure trip setpoints. The modification results in maintaining the values currently given in the technical specification for the pressurizer pressure and low steam generator pressure trip setpoints and changing the low steam generator level trip setpoint to > 46.5%. Accordingly, attached are reviced Technical. Specification Tables 2.2-1 and 3.3-4.

Very truly yours, )

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William Cav~anaugh III '

WC/JTE/mmb Attachments

STATE OF ARFJJ:3AS }

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) OJ COUUTY CF PULASKI )

William CavannuGh III, beinE, duly sworn, states that he is Executive Director, Generation & Construction, for Arkansas Power & Light Cc=pany; that he is authorized on the part of said Cccpany to sign a".d file with the !;uclear Re,:',ulatory Cor. mission this Supplementary Information; that he ,

has reviewed or caused to havo reviewed all of the statements contained in such infornation, ana that all such statem-nts made and natters cet forth therein are true ana correct to the best of his knowledge, i n fo rta-tien and belief, r

g l,- e n 'V 4'

Willi am Cavp(;h III /

CUEOCRIBED idD EWOE:. TO before me, a ';otary Pcblic in and for the County and State above named, thi s /.l 'b' day of ~ // /#//61/ /, 1978.

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l TABLE 2.2-1

[] REACTOR PROTE_CTIVE INSTRUMENTATION TRIP SETPOINT LIMITS 9

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$; TRIP SETPOINT ALLOWABLE VALUES FU_NCTIONAL UNIT A: 1. Manual Reactor Trip Not Applicable Not Applicable 15

-i

2. Linear Power Levtl - High na

d. Four Reactor reclant Pumps < 123% of RAIED THERMAL POWER < 123.712% of RATED THERMAL POWER' Operating *

b. Three Reactor Coolant Pumps

• Operating *

c. Two Reactor Coolant Pumps Operating - Same Loop

• Two Reactor Coolant Pumps

• d.

Operating - Opposite Loops na j, 3. Logarithmic Power Level - .

High (1) < 0.75% of RATED THERMAL POWER < 0.819% of RATED THERMAL POWER

4. Pressurizer Pressure - High < 2345 psia < 2353.887 psia ,

5. Pressurizer Pressure - Low g 1740 psia (2) 1 1686.75 nsia (2)

6. Containment Pressure - High 1 18.4 psia 1 19.024 psia

7. Steam Generator Pressure - Low _ 728 psia (3) 1 706.6 psia (3)

8. Steam Generator Level - Low 1 46.5% (4) E 45.61% (4)

T~These values left blank pending NRC approval of ECCS analyses for operation with less than four reactor coolant pumps operating.

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TABLE 3.3-4 (Continued) s 5 EtiGIriEERED SAFETY FEATURE ACTUATION SYSTEM IftSTRUMEf4TATION TRIP VALUES ,

E

' ALLOWABLE h FUtiCT10tlAL Ut1IT TRIP VA'1E VALUES 5

• 8. EMERGEflCY FEEDWATER (EFAS)

a. Manual (Trip Bu'ttons) flot Applicable flot Applicable

b. Steam Generator (A&B) Level-Low > 46.5% (3) > 45.61% (3)

c. Steam Generator t.P-High (SG-A ,1 39 psi 1 48.35 psi

d. . Steam Generator t,P-High (SG-B > SG-A) 5 39 psi s 48.35 psi

e. Steam Generator (ASB) Pressure - Low > 728 psia (2)

> 706.6 psia (2) co (1) Value may be decren cu manually, to a minimum of > 100 psia, as pressurizer pressure is reduced, provided 1 the margin between the pres;urizer pressure and tiiis value is maintained at 5 200 psi; the setpoint co shall be increased automatically as pressurizer pressure is increased until the trip setpoint is reached.

i. 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 5 200 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.

(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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