ML20064C169

Application for Amend to License NPF-4,changing Tech Specs to Revise Setpoints & Allowable Values.Class 3 Fee Encl

ML20064C169
Person / Time
Site:	North Anna
Issue date:	10/13/1978
From:	Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton, Parr O Office of Nuclear Reactor Regulation
References
565, NUDOCS 7810170163
Download: ML20064C169 (8)

Text

VInorNIA ELECTRIC AND PowEm CourAxr Ricaxown.VzmorNIA 23209 1

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October 13, 1978 -

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q' Mr. Harold R. Denton, Director Serial No. 565 Office of Nuclear Reactor Regulation LQA/ESG:..sh Attn: Mr. O. D. Parr, Chief Light Water Reactors Branch No. 3 Docket No. 50-338 Division of Project Management U. S. Nuclear Regulatory Commission License No. NPF-4 Washington, DC 20555

Dear Mr. Denton:

( '

AMENDMENT TO OPERATING LICENSE NPF-4 NORTH ANNA POWER STATION UNIT NO.1 PROPOSED TECHNICAL SPECIFICATION CHANGE NO. 15, Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company hereby requests an amendment, in the form of changes to the Technical Speci-fications, to Operating License No. NPF-4 for the North Anna Power Station, Unit No. 1. The proposed changes are enclosed and have been designated as Change No. 15 In accordance with License Condition D.(3)g, a report detailing instruunt setpoints and setpoint allowables for each Reactor Protection Sys-tem and Engineered Safeguards Features instrumentation channel was submitted with our letter Serial No. 541, dated September 29, 1978. This report also discussed the methodology used in determining these setpoints and allowables.

As a result of this study, revisions to several setpoints and allow-able values in the present Technical Specifications have been determined to be necessary. These revisions are noted in Attachment 1. In each case, the changes will provide assurance that the system parameters assumed in various safety analyses will be met when the technical specification setpoints and sta-tistically determined allowables are taken into consideration.

The proposed changes have been reviewed by the Station Nuclear Safety

and Operating Committee and the System Nuclear Safety and Operating Committee.

It has been determined that these changes do not involve an unreviewed safety question as defined in 10 CFR 50.59.

~l[rt o 17 Ol& 3 l' i

VinotutA hac7mc Awo Powra Commxt to Mr. Harold R. Denton 2 The proposed changes have been evaluated in accordance with the criteria of 10 CFR 170.22, and this request has been determined to be in Class lil. The i changes provide additional assurance that system parameters are maintained within the limits assumed in the safety analyses. Therefore, the Staff should be able to conclude that this request does not involve a significant hazards consideration.

Accordingly, our check in the amount of $4000.00 is attached in payment of the amendment fee.

Very truly yours,

6. ???. J a e y C. M. Stallings Vice President-Power Supply and Production Operations Attachments:

1. Proposed Technical Specification Change No.15

2. Check No. 31957, in amount of $4000.00 cc: Mr. James P. O'Reilly, Director Office of Inspection and Enforcement Region 11 k..

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l COMMONWEALTH OF VIRGINIA )

) S. S.

C1TY OF RICHMOND )

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Before me, a Notary Public, in and for the City and Common-wealth aforesaid, today personally appeared C. M. Stallings, who being duly sworn, made oath and said (1) that he is Vice President-Power Supply and Production Operations, of the Virginia Electric and Power Company, (2) that he is duly authorized to execute and file the fore-going Amendment in behalf of that Company, and (3) that the statements in the Amendment are true to the best of his knowledge and belief.

Given under my hand and notarial seal this g day of 4 trhe ,w My Commission expires ) ,, n s -r r t- u p, >4N .

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MJY W YnY Notary Public

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(SEAL)

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TABLE 2.2-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS

=

TRIP SETPOINT_ ALLOWABLE VALUES -

R FUNCTIONAL UNIT _

c 13. Steam Generator Water > 1%f narrow range instrument

>14% of narrow range ins'trument 5 Level--Low-Low span-each steam generator span-each steam generator

--e

14. Steam /Feedwater ' Flow < 40% of full steam flow at

~

< 42.5% of full steam flow at Mismatch and Low Steam RATED THERMAL POWER coincident ~ATED R THERMAL POWER coincident

- Generator Water Level with steam generator water level with steam generator water level

> 25% of narrow range instru-

> 24% of narrow range inst.ru-ment span--each steam generator ment span--each steam generator

. 15. Undervoltage-Reactor > 2905 volts-each bus > 2870 volts-each bus l Coolant Pump Busses ,

m 16. Underfrequency-Reactor > 56.1 Hz - each bus > 56.0 Hz - each bus Coolant Pump Busses 4,

17. Turbine Trip ,

A. Low Trip System > 45 psig

> 40 psig

[ Pressure B. Turbine Stop Valve > 1% open > 0% open Closure o 18. Safety Injection Input Not Applicable Not Applicable 8 from ESF 3> ' -

Md 19. Reactor Coolant Pump Not Applicable Not Applicable i

i

[$

"5 Breaker Position Trip l . ON 5 w ,

TTI u,

S

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=

TABLE 3.3-4 k

=

ENGINEERED SAFETY FEATURE ACTUATION SYSTEl4 INSTRUl1ENTATION TRIP SETPOINTS~

TRIP SETPOINT ALLOWABLE VALUES FUNCTIONAL UNIT

- 1. SAFETY IllJECTI0tl, TultBINE TRIP AND FEEuWATER ISOLATI0tl

a. fianual Initiation tint Applicable Not Applicable

b. Automatic Actuation Logic Not Applicable Not Applicable

c. Containment Pressure--High 1 17 psia 1 18.5 psia l

d. Pressurizer Pressure -- Low > 1765 psig > 1755 psig g

15% > 14% l

) Coincident with Pressurizer Water Level--Low ,

5 e. Differential Pressure < 100 psi

--< 112 psi Between Steam Lines--High

f. Steam Flow in Two Steam Lines-- < A function defined as < A function defined as High Coincident with Ta --Low-Low follows: a ap correspond follows: a ap corresponding orSteamLinePressureYEow ing to 40% of full steam to 44% of full steam flow flow between 0% and 20% between 0% and 20% load and load and then a ap increas- then a op increasing linear-ing linearly to a op corre- ly to a ap corresponding to sponding to 110% of full 111.5% of full steam flow .

steam flow at full load at full load T > 543*F 541'F T"$>psigsteamline-l

>NOpsigsteamline >58 pressure pressure r .

i 4 9

5 x

$ TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURE ACTUAT10fl_SYSTEll INSTRUMENTATION TRIP SETp0INTS .

i FUNCTIONAL UNIT TR_IP SETPOINT ALLOWABLE VALUES

-- 2. CONTAINMENT SPRAY

a. Manual Initiation Not Applicable Not Applicable i

b. Automatic Actuation Logic Not Applicable Not Applicable

c. Containment Pressure--High-High 1 27.75 psia 1'29.25 psia

3. CONTAINMENT ISOLATION

[, a. Phase "A" Isolation U 1. Manual Not Applicable Not Applicable E. From Safety Injection Not Applicable Not Applicable Automatic Actuation logic ,

b. Phase "B" Isolation

1. Manual Hot Applicable Not Applicable

2. Aut'omatic Actuation Logic Not Applicable Not Applicable

~

3. Containment Pressure--High-High 1 27.75 psia 1 29.25 psia O

._ _. . ......1 ...... . . . . . . . . _ . . _ . . .. _ _,, ,. , , , , _ _ , _ . . , _ - . .

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' i TABLE 3.3-4 (Continued) 5 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 9__ * '

3E FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES * ::

g A

2

4. STEAM LINE ISOLATION .

f a. Manual Not Applicable Not Applicable l

b. Automatic Actuation Logic Not Applicable Not Applicable

c. Containment Pressure--Intermediate 117.8 psia 119.3 psia '

High-High

d. Steam Flow in Two Steam lines-- < A function defined as

< A function defined as .>

High Coincident with T a --Low follows: a ap correspond- follows: a op Corresponding i OrSteamLine'PressureYEow ing to 40% of full steam to 44% of full steam flow I w flow between 0% and 20% between 0% and 20% load and 3 load and then a op increas- then a op increasing linearly i w ing ' linearly to a op corre- to a op corresponding to A, sponding to 110% of full 111.5% of full steam flow  :

c' steam flow at full load. at full load. .

l T 1 543'F T,yg 1 541*F avg i 1 600 psig steam line 1585 psig steam line pressure pressure ,

5. TURBINE TRIP AND FEEDWATER ISOLATION .

. a. Steam Generator Water level-- < 75% of narrow range < 76% of narrow range High-High Instrument span each steam Instrument span each steam generator generator -

9 4

e*--=., .=-==sa.**,% -..-m

,m. .<-..-.%.,...... ,~y..._%

e e , %-r = ==.-*....e.-

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.II TABLE 3.3-4 (Continued)

= ,;,

S ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS -

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$ .i 5 . FUNCTIONAL UNIT -TRIP SETPOINT ALLOWABLE VALUES

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E 6. AUXILIARY FEEDWATER PUMP START 7 [  :

a. Steam Gener.ator Water 11St of narrow range 11C of. narrow range i Level Low-Low instrument span each instrument span each I' steam generator steam generator ,.

. ~ b. S.I. See 1 above (All'S.I.'Setpoints)  !

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c. Station Blackout 1 7.5% Transfer Bus Voltage 1 52.5% Transfer Bus Voltage 5 ,

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d. Trip of Main Feed Pump N.A. . N.A.

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