ML20077E741

Change 63 to Procedure OP/1/A/6100/01, Controlling Procedure for Unit Startup

ML20077E741
Person / Time
Site:	Mcguire, McGuire
Issue date:	05/19/1983
From:	Firebaugh L, Brandi Hamilton, Mayes R DUKE POWER CO.
To:
Shared Package
ML20077E716	List: ML20077E714 ML20077E720 ML20077E732 ML20077E741
References
NUDOCS 8307280429
Download: ML20077E741 (5)

Text

'

Form 34811 (7 81)

(Formerly SPD 1003@

I DUKE POWER COMPANY (1) IDNo:OP/it4fb800[0/

PROCEDURE MAJOR CHANGE Change No: 63 PROCESS RECORD Permanent / Restricted To (2) STATION: //li [].at; (3) PROCEDURE TITLE: bm1prMi ,u kW/)n,v b Mp8 M,inI;,a (4) SECTION(S) 0F PROCEDURE AFFECTED: b v u w 4.'4 (5) DESCRIPTION OF CHANGE: (Attach additional pages, if necessary.)'

W-l.L ct

@$ @[ -

(6) REASON FOR CHANGE:

bWW 'M b bh4bWa GNl du /!/[C (7) PREPARED BY: d lN4 */d DATE: $!/Y(3 u' -

(8) SAFETY EVALUATION This change:

~

Yes No d Represents a change to the station or procedures as described in the FSAR, or a test or experiment not described in the FSAR?

Yes No / Requires a change to the station Technical Specifications?

Yes No / Involves an unreviewed safety question?

If the answer to any of the above is "Yes", attach a detailed explanation.

As appropriate attach a completed " Nuclear Safety Evaluation Check List" for=.

By: ,bdNI4y19 Date: 3, '/ / O (9) REVIEWED BY: [2 MNr. DATE: f- / '7 - 5 3

/}

Cross-Disciplinary Review By: /54(td4 9 e' N/R:~~75Rf* v', ^

(10) TEMPORARY APPROVAL (IF NECESSARY):

By: (SRO) Date:

By: Date:

(11) APPROVED BY: ,

DATE: [ 3 l (12) MISCELLANEOUS:

Reviewed / Approved By: Date:

Reviewed / Approved By: Date:

(13) Page 1 of 1 8307280429 830722 Rev 14 PDR ADOCK 05000369 9/20/77 P PDR

Fortir 34895 (6-82)

"armerly SPD -1003 3A PROCEDURE MAJOR CHANGE N e No- U3 PROCESS RECORD CONTINUATION FORM _

Page 1 of ^

(1,),,I ,

f

.. ; ..,6,, aw er l 6 Jtu%s?s' h*ms a Lu%. L niiuwl a 2.,,.,,wi o y av

'Y 1 11b'1 .n.* A . , f2 /l>r*1t'v1 (L'1li hlmituo h e.L IL MJ! lot) 4Y I ' a y h7/ On An],1., n I (1 lLY hl' 1111* . l M1M L'.'fL T lti FD1 W 11412A' $ lhH  ? (fl. .* ll) L@]) '

A19 l' Lb+1 ' Y ?'n't ')

v ,

e M11smn A 2]\llAYL . bL3A(FC V LM L1: N O& Wn )

'Nus$l- mas,2) ]'n -thi M Dlw o) c' o ru n. .. a '

i l

I i

w7n2M/wwY@h ENCLOSURE 4.4

, PAGE 1 0F 3 Modes 1 and 2 Checklist Date/ Initial A. The following items shall be completed prior to entering Mode 2:

/ 1. Check the Off Line Computer PT schedule and verify all scheduled PT's required for Modes 1 and 2 are up-to-date.

/ 2. Verify less than or ecual to 40 GPM controlled leakage at 2235 20 psig and document in the R.O. Log.

/ 3. Two licensed o.'erators are in the Control Room.

/ 4. The following instrumentation is operable per Tech Specs:

(IAE will sign off).

A. Reactor Trio System Instrumentatinn (Tech Spec. 3.3.1, Table 4.3-1)

/ Power Range Neutron Channel

/ Power Range, High Positive Rate

/ Power Range, High Negative Rate

/ _ Overtemoerature Delta T

/ Overpower Delta T

/ Pressurizer Pressure-Low

/ Pressurizer Pressure-High

/ Pressurizer Level-High

/ Loss of Flow

/ Steam Generator Water Level-Low-Low

/ Undervoltage-NC Pumps

/ Underfrequency-NC Pumos

/ Safety Iniection Input from ESF

/ Power Range Interlock P7 (Functional Test completed within previous 92 days) l

.' EM

,/ . - PAGE 2 0F 3

/ .

Modes 1 and 2 Checklist

/ Power Range Interlock P10 (Functional Test comoleted within orevious 92 days)

/ Power Range Interlock P8 (Functional test completed within previous 92 days)

/ Turbine trip-low fluid oil pressure (Functional test completed within previous 7 days).

/ Turbine trio-Turbine Stop Valve closure (Channel functional test completed within orevious 7 days).

/ 5. Individual full length rod droo times less than or equal to 2.2 seconds. (IAE will sign off).

/ 6. The hydrogen control distributed ignition system is operable (IAE will sign off).

/ 7. Two containment hydrogen monitors are operable. (IAE will sign off).

/ 3. Two containment hydrogen recombiners are Operable.

/ 9. Verify less than or equal to 1 gpm leakage at 2235 ?.0 psig from any NC Pressure isolation valve specified in Table 3.4-1 in Tech l Specs. (Test Group will sign of,f).

l i

/ 10 Tech. Spec. Action Log has been reviewed for items that may effect entering Modes 2 or 1.

/ 11. No outstanding QA items affecting Mode 1 or ?..

12. Verify applicable enclosures for Modes 1 and 2 of the following PT's have been completed within the surveillance period.

/ 1. PT/1/A/4600/03A (Semi-Daily Surveillance Items)

/ 2. PT/1/A/4600/038 (Daily Surveillance Items)

/ 3. PT/1/A/4600/03C (Weekly Surveillance Items)

f.' . ..

EN'CLOSijRE 4.4 PAGE 3 0F 3

~

Mod s 1 and 2 Checklist

/ 4. PT/1/A/4600/03D (Monthly Surveillance Items)

/ 5. PT/1/A/4600/03E (Quarterly Surveillance Items)

B. The following items should be completed prior to entering Mode 2 or as soon as oractical thereafter:

/ 1. Ice Condenser 3 ton crane is parked outside of ice condenser.

/ 2. Cooling fans and oil cumps are in operation on main setuo transformers.

/ 3. Place Acoustic 1.eak Detection Monitor in Auto and ensure points 1-10 are being scanned.

/ 4. Stop or verify the containment auxiliary carbon filter units are off when no longer required.

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