Text

Proposed Tech Specs for RTS Instrumentation,Srs & Bases & ESFAS Instrumentation,Trip Setpoints,Srs & Bases
	ML20128E681
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	01/29/1993
From:	; CONNECTICUT YANKEE ATOMIC POWER CO.
To:	;
Shared Package
ML20128E679	List: B14342, Application for Amend to License DPR-61,revising TS for RTS Instrumentation,Srs & Bases & ESFAS Instrumentation,Trip Setpoints,Srs & Bases.Draft Rev 0 to Project Assigment 90-013, CT Yankee Modernize Fwd Encl; ML20128E681;
References
	NUDOCS 9302100545
	Download: ML20128E681 (92)
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' Docket No'.-50-213-B14342-l Attachment 1 Haddam Neck Plant .

Proposed Revision to Technical Specifications Modernize:Feedwater.: Control l:

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l IJanuary-1993 9302100545x930129'

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-- . . . . ~ . - . . . - -. .-. ._. .. - - . - - . . . ...- .

TABLE 3.3-1 (Continued)

=, g ' REACTOR TRIP SYSTEM INSTRUMENTATION

= cs "E

'* MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE

%;'FUNCTIONALUNIT - 0F CHANNELS .'TO TRIP' OPERABLE MODES ACTION n

' 8. - ' Steam Flow-High 4.(1/steamline) 2 1/ steam line 1, 2 9f 9.: . Steam Generator Water:-

Level-Low .

3/SGlevel and 2/SG 1evel coincident 2/SGlevel.

and 1, 2 6f ]

Coincident With , with Steam /Feedwater. Flow- 2/ steam / feed- 1/ steam / feed- - 1/stea# feed- -l' Mismatch. water- flow ' water flow water flow:

. mismatch:in mismatch mismatch.

each SG -in same loop .in each SG

. 10. Undervoltage : Reactor- 2 (1/ bus) 1 2 (1/ bus)' I I*) 8 j_

JCoolant Pumps 4 '11. . Safety Injection- _

2 1 '2 1, 2 11A'

'I a

A:

^u.

e , < r .

wv-- -

TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 4:

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, suspend all operations involving positive reactivity changes and restore the inoperable channel to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or open/ verify open the Reactor Trip System breakers within the next hour.

ACTION 5:

Action has been deleted.

ACTION 6:

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, the inoperable channel may be bypassed up to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for surveillance testing of other channels per Specification 4.3.1.1.

ACTION 7:

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, reduce THERMAL POWER to below 74% of RATED THERMAL POWER (P-8) within I hour and place the inoperable channel in the trip position within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

ACTION 8:

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, reduce THERMAL POWER to below 10% of RATED THERMAL POWER (P-7) within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 9:

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, STARTUP and/or POWER OPERATION may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided that the inoperable channel is placed in the tripped condition within I hour.

HADDAM NECK 3/4 3-6 Amendment No. J/E 0093

TABLE 4.3-1 (Continued) 4 REACTOR TRIP SYSTEM INSTRUNENTATION SURVEILLANCE REOUIREMENTS

'M*

TRIP ANALOG ACTUATING- MODES FOR

E CHANNEL DEVICE WHICH R CHANNEL CHANNEL OPERATIONAL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK- . CALIBRATION TEST TEST IS REOUIRED

8. Steam Flow--High S R(5) SW~ N.A. 1, 2 l ,

9. -- Steam Generator Water J Level--Low Coincident-with, Steam /Feedwater.

F1ow Misnatch S R ' SW N.A. 1, 2 l

'10. Undervoltage -' Reactor Coolant: Pumps N .' A . R N.A. R' 1(*) ,

y 11. Safety [ Injection N.A. N.A. N.A. .R 1, 2

. 7 11. Reactor Coolant Pump i 5 Breaker Position Trip N.A. ~N.A. N.A. R 1(*) i

13. Main Steam Line Trip

' Valve Closure - N.A. N.A. N. A.- R 1(*)

-14. . Turbine Trip. N. A.- N.A. N.A. 'R 1(a) 2 a:

% v %g A H er-

TABLE 3.3-2 (Continued)

~

oc ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MINIMUM "la CHANNELS APPLICABLE

E TOTAL NO. CHANNELS OF CHANNELS TO ACTUATE OPERABLE MODES ACTION Ei FUNCTIONAL UNIT E

5. Containment' Isolation (Containment Air Recirculation System, Feedwater Isolation, Safety Injection)

a. Containment Pressure-High 4 2 3 I, 2, 3, 4 20, 24

b. Safety Injection See Item I. above for all Safety Injection initiating functions and requirements.

4" 6. Feedwater Isolation

- t' a. Narrow Range Steam Generator 3/stm. gen. 2/stm. gen. 2/stm. gen. I 24 3; Water Level--High in each in any in each operatint, operating operating-loop loop loop E

a n

P 11

. ?>

b

TABLE 3.3-2 (Continued)

TABLE NOTATIONS

Trip function may be bypassed in this MODE when RCS pressure is less than 1800 psig.

- The channel (s) associated with the 1rotective functions derived from the out-of-service reactor coolant loop sha11 be placed it the tripped mode.

(a) THERMAL POWER above 10% of RATED THERMAL POWER.

(b) for Surveillance Testing, at most only one train may be taken out of service at a time.

(c) Not used. l.

(d) For surveillance testing purposes, (item 3.a of. Table 4.3.2) the minimum channels OPERABLE may be less than those specified in Table 3.3 2 for items 3.a.1 and 3.a.2. l ACTION STATEMENTS ACTION 20 -

With the number of OPERABLE channels one less than the-Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 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 .

ACTION 21 -

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, startup and/or power operation may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within I hour.

ACTION 22 -

With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-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 at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 23 -

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore tha inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or bo in at least 2

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 , i

I I

l HADDAM NECK 3/4 3-17 Amendment No J/E, JfJ 0098

TABLE 3.3-3 (Continued) is . ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS E3

!E me FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE R

4. Emergency Bus Undervoltage

a. 4.16 kV Bus Undervoltage - 12870** volts 2,84** volts Level I

b. 4.16 kV Bus Undervoltage - 23684 volts 23664 volts level 2 with a 9 second with a 8 second time delay. to 10 second time delay.

c. 4.16 kV Bus Undervoltage - 14019 volts with 23999 volts with a Levol 3 a 9 second time 8 second to 10 u, delay. .

second time delay.

32

c. 5. Containment Isolation A, (Containment Air Recirculation System, Feedwater c) Isolation, Safety Injection)

a. Containment Pressuie - High 54.7 psig $5.0 psig

b. Safety Injectior See Item 1. above for all Safety Injection Trip Setpoints and allowable values.

Er 6. Feedwater Isolation g- a. Steam Generator Water Level--High 574% of narrow-range $80% of narrow-range l-g instrument span instrument span E

Rated Thermal Power U

!= ** Setpoint is by tap position. Time delay of device is inverse function of voltage. Device must change

,s state within 0.95 - 1.05 seconds when the input voltage to the device goes from normal to 50% of the trip

%g setting voltage instantaneously.

_ - _ --___ .____ ____- __ =

TABLE 4.3-2 (Continued) i

E ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION ,

",8 - SURVEILLANCE REQUIREMENTS gl TRIP. '

ANALOG ACTUATING MODES FOR

_z p; CHANNEL DEVICE WHICH

^ CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL' SURVEILLANCE FUNCTIONAL UNIT CHECK' CALIBRATION TEST TEST IS REOUIRED

4. Emergency Bus Undervoltage

a. '4.16'kV Bus- N.A. R N.A. M* 1, 2, 3, 4 Undervoltage -

Level I

b. 4.16 kV Bus 'N.A. R N.A. M* 1, 2, 3, 4 Undervoltage -

4 Level 2

$- c. 4.16 kV 5.s N. A. - R N.A. M* 1, 2 w Undervoltage -

g, Level 3

.m. . .

5. Containment' Isolation

-(Containment Air Recirculation:

System, Feedwater. Isolation,

Safety. Injection)

'a. Containment Pressure .D R SW N.A. 1, 2, 3, 4

--High' 3- b. Safety Injection See Item 1. above for all Safety. Injection Surveillance Requirements.

6. Feedwater Isolation t

e+ - a.x Steam Generator Water. .S R SW R 1

.)

t Level--High:

.w

(*

g.~

Tripcactuating device operational test .is defined as a test of each individual channel. A complete logic test

_will be. performed on a refueling outage basis. On a monthly basis, an un<fervoltage condition'will be~ initiated i

at thef sensing device to verify the. operability of the trip actuating device and verify that the associated

-alarm relays operate.

3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM INSTRUMENTATION AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION The OPERABILITY of the Reactor Trip System and Engineered Safety Features Actuation System instrumentation and interlocks ensure that: (1) the asso-ciated ACTION and/or Reactor tri) will be initiated when the parameter monitored by each channel or com)ination thereof reaches its Setpoint, (2) the specified coincidence logic is maintained, (3) sufficient redundancy is maintained to permit a channel to be out-of-service for testing or mainte-nance, and (4) sufficient system functional capability is available from diverse parameters.

The OPERABILITY of these systems is required to provide the overall reli-ability, redundancy, and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The integrated operation of each of these systems is consistent with the assump-tions used in the safety analyses. The Surveillance Requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability.

The Feedwater Isolatiori circuit is considered to be OPERABLE provided either the Feedwater Regulating Valve or the Feedwater Isolation M0V is available for automatic closure.

The Engineered Safety Feature Actuation System Instrumentation Trip Setpoints specified in Table 3.3-3 are the nominal values at which the bistables are set for each functional unit: A Setpoint is considered to be adjusted consistent with the nominal value when the "as measured" Setpoint is within the band allowed for calibration accuracy.

To accommodate the instrument drift assumed to occur between operational tests and the accuracy to which Set)oints can be measured and calibrated, Allowable Values for the Setpoints lave been specified in Table 3.3-3.

Operation with Sctpoints less conservative than the Trip Setpoint but within the Allowable Value is acceptable since an allowance has been made in the safety analysis to accommodate this error.

The Engineered Safety Features Actuation System senses selected pl?nt parameters and determines whether or not predetermined limits are being exceeded. If they are, the signals are combined into logic matrices sensi-tive to coabinations indicative of various accidents, events, and tran-sients. Once the required logic combination is completed, the system sends actuation signals to those Engineered Safety Features components whose aggregate function best serves the requirements of the condition. As an example, the following actions may be initiated by the Engineered Safety Features Actuation System to mitigate the consequences of a steam line break i

l HADDAM NECK B3/4 3-1 Amendment No. J #

oost

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f INSTRUMENTATION SASES 3/4.3.1 ar;d 3/4.3.2 REACTOR TRIP $YSTEM INSTRUMENTATION AND ENGINEER [D-SAfflLEEATURES.- ACTUATION SYSTEM INSTRUMENTATION f continued) or less of-coolant accident: (1)-Safety Injection aumps start and automatic ~ <

valve.t position, (2) ReactorLtrip,- (3)-startup of t1e emergency diesel generators,(4) containment isolation, (5) Turbine-trip,-(6) auxiliary.

feedwater pumps start and automatic valves position,-(7) containment- !

cooling fans start and automatic valves position, and (8). essential ~ service water pumps start and automatic valves position. ;

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HADDAM NECK. .B3/4)3-la Amendment No.

'9991 s

k_.:

Docket No. 50-213 B14342 l

f 1

Attachment 2 Haddam Neck Plant Draft Final Project Description Modernize Feedwater' Control 4

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January 1993.-

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1 i

PA06 PA0 JECT ASNGNMENT NO. R E V. NO.

1 o,81 90-013 0 Northeast Utilltles Service Company n NUCLEAR ENGINEERING & OPERATIONS ;

PROJECT DESCRIPTION vmOJtCT 71TLE ,

! DEMT 4 -CONNECTICUT YANKEE

' MODERNIZE.FEEDWATER CONTROL ',

i

' ~

WSTT 1

a i

? f Please Note that this title page is'Page 1 of-81 f

i PREPARED BY: _ Date:

J. G, Fougere PSD Project Engineer APPROVED ~BY- : Date :=

o 'M..F. Samek PSD Supervisor '!

. _- Date:

G. R. Pitman PSD Manager Y. Datei I -JI B.'Overbaugh'.

PSD Project Coordinator.

. .Date:

'G. Hi Bouchard

-CY Unit Superintendt.nt i,

JAU/WORKLORDER NO.:- .

C2/34890101 ..

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,p-e 2TB34P.07H..

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i , J twen cre .PAG-E PA0ACT Af/4NWENT NO Mv, No.] - ,

L 2 o,81 90-013 -0 l L - Northeast Utilities Sorvice Company q 4

NUCLEAR ENGINEERING & OPERATIONS - -

i PROJECT DESCRIPTION

}l

~ ~

. emonet titor, DRAFT ;j

- CONNECTICUT YANFEE -1 l

MODERNIZE FEEDWATER CONTROL. q l

! 'Phmtet l

J

! TABLE OE CONTENTQ.

. SECT *i.Q1{ DESCRIPTION PAfiM 'l

,. s

.- . 5

! -1.0 PROJECT: SCOPE . . . . . . . . . . . , , . ..- . . . .

.- . 7 1

} 2.0 NUu' LEAR GNGINEERING ' AND OPERATIONS GROUP INTERFACES D 2.1 Engine.tring . . . . . . .. ... . , 1.' , , . . . .. .

.- 7. -!

2.1.1 ' Project Engineer.._. . .:-. .. . 4

. .. . .- 7' 2 .1. 2 -- tNUSCO Electrical Engineering 1(PSD) .v. . :. 8

2 .1. 3 NUSCO Civil'.&1 Mechanical Engineering -( PSD) . 110 -

c 2.1.4 NUSCO Engineering Mechanics x (ED) .; . .- . . -10 >

j 2.1.5 NUSCO Civil EngineeringC(ED)' 1.. 1. - . .. . .., .- 11 2 .1. 6 ' NUSCO Stress Analysis.(EDE . .. . ' . ... :11- a i

F 2.1.7 NUSCO Electrical and I&C-Programs-(ED) .- . . 11- '

2.1.8 NUSCO Fire Protectien and Facilitie/ (ED) . 12

- 2.1.9 NUSCO Safety.Anelysi's- . . . a :. ..:. . . . .. .

. 12 2.1.10 NUSCO-Probabilistic Risk Assessment .3 . .- 12' NUSCO Nuclear Lict.nsingc .c-.c..=-. .. . .- 13 2.1.11. . :. - ~ '

! 2.1.12 NUSCO Reliability Enginee, ring 7 y.- .-.. ..L.. . 113

'2.1.13 CYAPCO Health Physics' ,, . m : . c, . - . . ' . - - . _ . ' 13; 2.1,14 CYAPCO Plant: Engineering'. . . - . - -. n.

. :... . ~13-1 2.1.15 CYAPCOLI&C-Engineering 1.. , -. .. ;. :. .

. .: . .= 151 U

2.1.16 NUSCO Quelity Services Department. .1 . = : .s a - . 115e 2.1.17 iNUSCO Procurement' Engineering 16:

' 2.210esign ...-s L.i . . . . . 16

.-.- .......-..o.:..:. .. .

^

,16<

-2.2.1 .NUSCOLElectrical Design . .m.'..-4". . n .

2.2.2' NUSCO Civil &' Mechanical: Designi (PSD) -. . '17-

!~ o 2,3" Implementation . ., . . .;... . . . . . .. '..:x-... . -18 E 2.3.1; 'NUSCO Generation Construction- - . . -

..;-, .. . :18-2.3.i NUSCO' Gar.eration Td.at . . - -.' . . .

4

v. ...

19 .-

r "2.3.3 CYAPCO Instrumentation and Coatrols- .- . . -. !19? w!

, 2.3.4' ;CYAPCO Operations '

. ./. . +1 . ' . - . .: . .

~ . . 2 03 ~

2.4L Nuclear Training' ...;...;. . - . - . . . - . . . v. . - - . . .. .. ,

.' . . .: ., 121l l ;' 2 . 4 .1 - NUSCOLOperatorJTraining' . . . . _ - . ,

. 2.4 2 NUSCO Technica11 Training ,:..;.-c. . 7 1. .

. . . . 21 ,

i 2 .4 . 3 NUSCO Simulator Technical Support- . . . . . _ 211 al 2.5 Project-Mategementland Administrative Support . . '. 21J 1

2 TBS 4P.0?M:

5:

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50M63 2 MEV.244 PAGE PROJECT ASSIGNMENT No. Atv. No.

4 3 o,81 90-013 0 Nmtheast Utilities Servl:e Company NUCLEAR ENGINEERING & OPERATIONS i PROJECT DESCRIPTION PA0 JECT TaTL1 DRAFT j i

CONNECTICUT YANKEE l MODERNIZE FEEDWATER CONTROL j woe - --

2.5.1 NUSCO Project Coordinator. . . . . ' . . . . . 21 l 2.5.2- NUSCO Cost Engineering.and Scheduling (PSD) 21 i 2.5.3 NUSCO Purchasing . . .. .. . . . . . . . . 22

! 2.5.4 NUSCO Production Materials Group _. . . . .. 22 i

3.0 CONDITIONS AND L1MITATIONS .. .- . . . - . - . . . . . . . - . - . 22 4,O REGULATORY REQUIREMENTS . . . . . . . . . . . .. . . . 23 5.0 DESIGN . . . . . , . . . . . .. . . . . . . . . . .. . . 23 5.1 Bases of Current Design . . ., . . . . . . . . . . 23 <

5.1.1 Feedwater Control System . . . . . . .- . . . 23 5.1.2 Steam Flow /Feedwater Flow Mismatch Reactor

~

Trip . . . . . . . . . . . . . . . , . .. . 34 5.1.3 Steam Line Break Reactor Trip _ . . . .. . . 35 l-5.1.4 Steam Generator Overfill Protection' . . . . 36 l 5.1.5 Vital Inverters A and B . . . . . . . . . . '36

5.2 Method of . Change . . . . . . . . . . . . . . . . . . 37 l 5. 2 .1 Steam Generator Feedwater Flow Transmitter .- L37,

! 5.2.2 Steam Generator Steam Flow Transmitters . . . 38

, 5.2.3 Steam Generator Warrow-Range Level Transmit-ters . . . . . . . . . . . . . . - . . = . . . . . 39 l

L 5.2.4 Steam Line Break? Flow Transmitters . . . . . -41 i

s . 2 . 5 Steam Generator Prc.ssure Transmitters ., . 42 U

! 5.2.6 Main Control-Room Instrumentation Cabinets . :43

-Mairl Control BoardLModifications .. . . . . . 44 i- 5.2.7

,; 5.2.8- . Vital Inverters-A and B' . . . ... . . . . 44 L 5.3 Desigif Inputs .. . . . . . . . . . . . .. . - . - . ' .' '45

! 5 . 3 .1 - American National Standards Institute . . . 451 i- 5 '. 3 . 2 American Soci'etyjfor Testing and_ Materials . 46

~

5.3.3- Institute of' Electrical and Electronic Engi- ,

'46

-neers . . . . .. . . ., . . . . . . . . .- .

5.3.4 U.S. Nuclear. Regulatory-Commission (NRC) . . 49-

! 5.315' Instrument Society of America . .. ...- . . 51-5.3.6 Mechanical Engineering. Standards . . , ... 151

( 52

!- -5.3.7- Plant Design Documents / Inputs . . . . . . . .

'5.4 Detailed Design. - . - . - -. . . .. . . . . . . .. . . . 53 L

5.4.1 Procurement Specifications . . . . .. . , , 53 5.4.2 Design Drawings ,

. . . . .. . . - , . . . . 54-

2T354P.07N-L

acus > Cav.m PAQt PROJtCT AS$iONMENT No. may. No.

4 o,81 90-013 0 ,

Northeast Utilities Service Company NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION PROJECT f tTLE

-DRAFT T CONNECTICUT YANKEE j MODERNIZE FEEDWATER-CONTROL I

PROJECT r

5.4.3 Design Evaluations . . . . . . . . .- . . . . 56 5.4.4 Conformance to IEEE 279-1971 and IEEE 603-1980 . . . . . . . . . .. . . . . . . . 57 5.4.5 Transmitters , - . . . . . . . . . . . .. . . .- 63 5.4.6 Indicators . . . . -. . .. . . . -

.- . . .. . .- 64 E.4.7 Recorders . . . . . . . , , , .... . . . 65 5.4.8 Auto / Manual Stations-, . . . , .. .. . . .- 55 5.4.9 Annunciators , . . . . . - . .- .. . . . . ., . . -66 1 5.4.10 Computer Points. . . . . . . . . . . . . . . . . . 67 5.4.11 SPEC 200 Micro Usage . . - . - . .. . . . . . .. ~69-5.4.12 Equipment Power Sources' . .. . .; . . . - -

. 69 5.5 Implementation Plan .= , .. . . .. . .. . . . . . 69 7 5.5.1 General- .. .: . . ..:. . ... . . . . . . '

5.5.2 Pre-Outage Construction . . . . . . . . . < 70:

5.5.3 Outage Construction . . . ... . . -. . . ..

71 5.6 Test Plan- . . . . . . _ . . . . . . .. . . . , . . . 73 5.6.1 Construction Phase Testing . . . . .. . . . 73 3 5.6.2 Precperational Testing .s . -- -. .. . . . . - 76

5. 6. 3- Periodic Post Installation Test.ing . . . . :

~.. 80 5.7 Quality Questiens- . . _ . . . . . , . . . . . . . .. . '81 o

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2 TBS 4P.07M i:- - __ ______ -_ _ . - - .

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

. 4 PAQ$ PROJECT A$$iGNMENT NO. R(y, NQ,

-l 5 o,81 90-013 ,O l Northeast Utilities Service Company -

NUCt. EAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION A

6

0dLCT TITLE DRAFT i

CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL 9ROJtCT 1.0 PROJECT SCOPE

' This project continues the Connecticut Yankee instrumenta-tion modernization effort by replacing the' existing obsolete Hagan Feedwater Control System instrumentation with a state- l of-the-art digital upgrade. The-project goals are to in- '

crease system reliability and plant availability while 4

improving the plant's design adherence to current industry standards. The scope of the project includes the following:

1) The replacement of the eight Steam Generator feedwater- ;

flow transmitters (FT-1301-1A, -2A, -3A, -4A, -1B, -2B,

-3B, -4B) with eight redundant' Class 1E,_4-20 mA equiva--

lents (FT-1301- 1B, -2B, -3B, -4B, -1C, -2C, -3D, -4D).

2) The replacement of the four Steam Generator steam flow transmitters (FT-1201-1, -2, -3, -4) with eight redun-L dant Class 1E, 4-20 mA equivalents (FT-1201-1B, -2B,

-3B, -4B, -1C, -2C. -3D, -4D).

3) The replacement of the four-steam _ generator narrow range i level transmitters-(LT-1301-1, -2, -3,--4) with twelve

< redundant-Cless 1E, 4-20 mA Steam Generator narrow-range level transmitters. _(There will be twelve total; three t per loop.) This will include the relocation of= existing temporary steam generator 1 narrow-range' level circuitry '

from the Reactor Protection Cabinets to the secondary-side Reactor Protection Cabinets (LT-1301-1A, -2A, -3 A, :

-4A, -1C, -2C, -3C, -4C, -1D, -2D, -3D, -4D).

I 4) The replacement of the four Steam Line. Break-flow trans-l mitters.(FT-1202-1, -2, -3, -4)1with four_ redundant Class-1E, 4-20 mA equivalents (FT-1202-1, -2, -3, ~4) l 5) The replacment of the four_ containment mounted Steam Generator pressure transmitters (PT-1201-1, -2, .-3,.

L -4) with four redundant Class 1E, 4-20 mA Steam Genera-I- tor pressure transmitters (PT-1201-1B, -2B, -3B, -4B).

TheLexisting Steam Generator pressure transmitters 2 TBS 4P.btH

['l i

y - u --~c -

~

PAGE PAQJLCT A$$10NMENT NO.90-013 RbV, NQ.

6 4,81 Northeast Utilltles Service Company NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION Ph0 JECT T4TLE l

DRAFT i 4

CONNECTICUT YANKEE l MODERNIZE FEEDWATER CONTROL l PROJECT

' mounted in the terry turbine building (PT-1201-1B, -2B,

-3B, -4B) will be renamed (PT-1201-1C, -2C, -3D,.-4D).

6) The replacement of Steam Flow / Feed Flow mismatch Reactor.

Trip circuitry with solid state equipment and suitable field interface.

7) The replacement of Steam Line" Break Reactor Trip cir-cuitry with solid state equipment and suitable field-interface.

8) The replacement of Steam Generator Water Level Control circuitry with solid state equipment and suitable field interface.

9) The replacement and-addition of Main Control Board mounted equipment associated with the above changes (indicators, recorders, controllers, etc...), as well as

- the replacement of the Steam Generator wide-range level indicators and the Auxiliary Feed Flow indicators.

10) The addition of on-line testing capability for'the above Reactor Trip input' circuitry.

11) The enhancement of the Steam Generator overfill protec-tion circuitry including.the automatic closure of the feedwater isolation motor operated valves (FW-MOV-11,

-12, -13, -14) as well as the feedwater regulating valves (FW-FCV-1301-1,--2, -3,--4).

12)- The addition of automatic control for the feedwater-bypass valves for automatic steam generator level con-trol.at lower power levels.

13) The replacement of' Vital Inverters A and B with two Class 1E 5 kVA inverters and backup transformers.

14) This project will interface with Plant Design Change 1319, Feedwater Bypass Flow Modifications,.which wil'1

- 2 TBS 4P.07M

1

'#'""'* PAos Pahct AssioNurNt NO -

90-013- A5r NO, 7 o,81 Northeast Utilities Senrice Company _1 1

NUCLEAR ENGINEERING & OPERATIONS-PROJECT DESCRIPTION I

{

l PROJECT TITLE DRAFT CONNECTICUT YANKEE-

) MODERNIZE FEEDWATER CONTROL Paoact provide a bypass flow measurement of 0-600 GPM. This

' project will replace the control board indicators and provide additional wiring for the bypass flow input to 2

the Feedwater Control cabinets.

2.0 NUCLEAR ENGINEERING AND OPERATIONS GROUP INTERFACES 2.1 Enaineerina 2.1.1 Proiect Encineer a) Prepare and revise the-Project Assignment and Project Description, i

b) Coordinate the preparation of the Project Budget and Project Schedule, c) Prepare and revise Project Equipment Speci-fications, d) Interface with vendors to provide supplemen-tal design criteria, e) Review and approve preliminary.and final drawings (functional, logic, schematic,

. wiring, P&ID, and equipment installat' ion)..

f) Coordinate the preparation, review, and.-

approval of the Project Materials Lists.

g) Coordinate the preparation, review, and approval of Purchase Requisitions. Submit' quality related electrical; purchase requisi-tions to NUSCO Procurement Engineering 1for review and approval.

L h) Prepare the PDCR and coordinate the review, approval, and submission to the CYAPCO pngi-neering Manager, i

ITBS4P.07M

[

PAOL- PROJECT AS$iGNMENT No.

, 8 g,81 90-013 Abv. No.

i Northeast Utilities Service Company _ ;

NUCLEAR ENGINEERING & OPEHATIONS PROJECT DESCRIPTION l

PROJECT TITLE DRAFT-

! CONNECTICUT YANKEE e

MODERNIZE FEEDWATER CONTROL 5 PaoJaci ,

i) Initiate appropriate Technical Specification Change Requests.

- j) Coordinate the' preparation, review, and approval of Safety Evaluations.

k) Review and approve vendor test precedures and witness the Facility Acceptance Test.

4

1) Provide outage support for project implemen-tation, m) Review and approve as-built drawings and transmit to design, n) Prepare Turnover-Documentation.

o) Prepare documentation-in support of PDCR close-out--(FSAR change,-MEPL, Recommended I ' Spare Parts, and FMMS updates).

p) Perform Project Close-out.

g) ' Interface with CYAPCO Plant Engineering for preparation of Purchase Requisitions of consumable items-(wire lugs, splices, heat

shrink tubing, etc.).

d 2.1.2. NUSCO Electrical Encineerina (PSD)

.a) Supply detailed. instrumentation and control-4 ' design-requirements.

b) Ensure that the-instrumentation and-control-design is:in accordance with appropriate codes and standards.

P 2 TBS 4P.07M -

4 .

""" * Won pnosect assiswswi wo niv. wo.

9 o, 81 90-013 0 Northeast Utllhles Service Company NUCLEAR ENolNEERING & OPERATIONS PROJECT DESCRIPTION PhostC1 fif LE DRAFT CON!1ECTICUT YANKEE MODERMIZE FEEDWATER CONTROL Pmostc1 c) Perform independent review and approval of instrumentation and control design documen-tation, d) Coordinate all major. electrical modifica-tions.i.r the 1993 outage to reduce dupli--

cation of effort and define clear boundaries between the various Project Assignments.

e) Specify the electrical design inputs, f) Determine power requirements and provide sources.

g) Perform loading calculations, h) Provide technical input to Electrical De-sign, i) Review'and approve l cable--routing and elec--

trical drawings.

j) -Ensure that the electrical design is in accordance with appropriate codes and stan-dards.

k) Prepare electrical'PDCR_ input.

~

1) Prepare the Electrical' Purchase Requisitions. . Submit quality related elec-

-trical purchase requisitions.to NUSCO-Pro-curement= Engineering for review and~approv-al.

m) Prepare the Electrical: Safety Evaluation.

n) Perform electrical independent design veri -

fication reviews.- ,

HE44P.07M a

PA06 PhostCT AB6iowtNT No. pty No.

10 o,81 90-013 0 Northeast Utilities service company NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION PhostCT 1876E DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL PAQstCT o) Review and approve electrical as-built draw-ings.

2.1,3 NUSCO C11'11 __Mechanica1 Encineerina fPSD) a) Specify'the civil and' mechanical design in-puts, b) Ensure that the civil and mechanical design is in accordance with appropriate codes and standards.

c) Provide technical input to Civil and Mechan-ical Design.

d) Review and approve equipment mounting draw-ings.

e) Prepare civil and mechanical PDCR input.

f) Prepare the_ Civil Safety Evaluation..

g) Perform mechanical independent design veri-fication reviews.

2.1.4 NUSCO Encineerina Mechanics (ED) a) Perform equipment seismic qualification review and approval.

b) Specify seismic design inputs.

c) Specify the seismic design-requirements for the installation of instrumentation within the Main Control Room, d) Specify the seismic design requirements for the installation of transmitter racks'apd 2 TBS 4P,07N

1

'D * ' #'*** Pros pnostet Assiowwast wo 11 ,,81 90-013 nE. wo.

Northeast Utilities Service Company 4

NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPfl0N 1

Peostetfifts DRAFT CO!MECTICUT YANKEE 4 MODERNIZE FEEDWATER CONTROL PhostCT j mounts in the Turbine Building and in Con- l tainment. l e) Specify the seismic design requirements for i

Main Control Board mounted equipment.

f) Ensure that the seismic design is in accor-dance with appropriate codes and standards.

i g) Review and approve Civil and Mechanical I drawings, i h) Prepare-PDCR input.

1) Perform seismic-independent design verifica-tion reviews.

j) Review and approve Civil and Mechanical as-built drawings.

2.1.5 NUSCO Civil Encineerina (ED) a) Perform civil independent design verifica-tion reviews.

b) Perform structural analysis as required and provide input to PDCR.

l 2.1.6 NUSCO Stress Analysis (ED) a)- Specify the seismic design requirements for the installation =of instrument tubing in Containment.

b) Provide-technical review for'PDCR. input. ,

2,1.7 NUSCO Electrical and I&C Procrams ~ (ED) a) Specify EEQ design inputs',

'27Bs4P.07M

l 4

' * * *

Past enosicT ApisNvini wo.

, 12 o,81 90-013 '5( wo.

I Northeast Utilities Service Company ;

NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION l

l PAostC1 TITLE f

DRAFT l CONNECTICUT YANKEE '

i MODERNIZE FEEDWATER CONTROL Phostct b) Ensure that the EEQ design is in accordance '

3 with the appropriate codes and standards.

3 c) Update EEQ documentation.

I d) Prepare PDCR input.

I e) Perform independent design verification.

reviews.

. f) Review and approve EEQ Walkdown Checklists.

! g) Perform Appendix R review of PDCR and update Appendix R compliance report if necessary.

! 2.1.8 NUSCO Fire Protection and Facilities (ED) a) Specify design inputs.

b) Perform Fire Protection reviews.

c) Ensure that the design is in accordance with appropriate codes and standards.

d) Prepare PDCR input;.

e) Perform independent design' verification '

reviews.

2.1.9 NUSCO Safety Analvfig a)- Prepare PDCR input, b) -Prepare the Integrated Safety Evaluation.

2.1.10 1RISCO Probabilistic Risk Assessment a) Develop attributeand of implement theRanking the Analytic public safety'.

Model 2TB54P.07M.

, . . . ,.. .~, - -. , .

'D*"""***

>Aos enostet Assiowast 90 mrv wo 13 ,,81 90-013 0 Northeast Utilities Service Company NUCLEAR ENGINEERIMO & OPERATIONS PROJECT DESCRIPTION r,

PRostC1 title LRAFT COli!JECTICUT YA11KEE ,

140 DER 111ZE FEEDWATER COliTROL VnoJLC1 b) Evaluate the project for the Integrated Safety Assessment Program (ISAP).

c) Review the Conceptual Project Description with respect to impact of the project on the Corporate 11uclear Safety Goal.

2.1.11 ITUSCO 11uclear Licensina a) Identify regulatory requirements, b) Review and comment on the Project Descrip-tion and Design Inputs.

c) Provide liaison with all Regulatory Agencies as required, d) Coordinate agency review and approval.

e) Coordinate the approval of any Technical Specification Change Requests.

2.1.12 11USCO Reliability Encineerina a) Perform a Reliability Analysis on the plant modification in accordance with IEEE Stan-dard 577-1976, Section 4.

2.1.13 CYAPCO Health Physics a) Perform ALARA Design Review, b) Submit ALARA recommendations.

c) Prepare PDCR input.

2.1.14 CYAPCO Plant Encineerina e

2 TBS 4F,07M

- . . _ - - . . - - .~ . .. . - . . _ - - . - .

'" " C'*** nTs eno a ev 4 si m ist 8 o.

14 ,,81 90-013 ln5oo.

Northeast Utilities service Company

. ENGINEERING & OPERATIONS

' 40 JECT DESCRIPTION i

, *2Wsf'W DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL Paoetet i

a) Coordinate the plant's review of design ,

documents and obtain a-consensus of plant opinions for the detailed design..

b). Specify,-review, and approve the. project's Design Inputs.

c) Coordinate the preparation and performance of test procedures to complete i

preoperational testing.

d) Review and approve the PDCR and coordinate the PORC approval, f

e) Review and comment on vendor drawings, f) Review and comment on the vendor test proce-dures and witness the Facility Acceptance Test.

i g) Provide outage support for project.implemen-1 tation ! coordinate work orders, testing, significant DCN processing, NCRs, etc...)=.

h) Review the project construction schedule and '

coordinate plant activities.-

i) -Ensure that the modification ~is' complete,

that all precperational requirements are

~

complete, and that all open itemstare iden-tified and tracked.

j) Notify the Shift Supervisor of the. Engineer-ing Release for Operation, k) Coordinate the collection of all-as-built drawings.. ,

2 TBS 4P 07M

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

4 .

1 PAGE PROJECT AlliGNMENT No mgy. No

. 15 o,81 90-013 0

Northeast Utilities Service company NUCLEAR ENolNEERING & OPERATIONS PROJECT DESCRIPTl0N i 1

P40stCT TITLE DRAFT f CONNECTICUT YANKEE i

MODERNIZE FEEDWATER CONTROL ,

s Phostet 1

2.1.15 CYAPCO I&C Encineerina a) Specify, review, and approve the project's Design Inputs, b) Coordinate the preparation and performance of test procedures to complete-preoperational testing.

c) Revie.w and comment on vendor drawings.

i d) Review material specifications and the PDCR.

e) -Review and comment on the vendor' test pro-cedures and witness the Facility Acceptance Test.

f) Coordinate the Software Configuration.

g) Provide outage support for project implemen-tation (coordinate testing and troubleshoot-ing).

h) Review the project construction schedule and coordinate plant activities.

2.1.16 imSCO ouality Services Deoartment a) Review and approve material and installation specificationss (NUSCO QSD) b)- Review and approve quality related- procure-ment documentation.-(NUSCO PROS) ,

c) Perform supplier audits / inspections.>(NUSCO PVS) d). Perform material receipt inspections..(NUSCO PRQS) l 2TB54P.07N

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

sow n 8 ats844 PAos emostet AssiswtNT No.

16 o,81 90-013 afv ho.

Northeast Utilities service Company

. NUCLEAR ENGINEERING & OPERATIONS i PROJECT DESCRIPTION 4

~Paostet title DRAFT 4

CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL PhostCT N

! e) Perform field surveillances. (!WSCO PROS /QSD)

J k f) Coordinate NCR issuance, tracking, and clo-J sure. (NUSCO PROS /QSD) l g)- Perform AWO reviews and inspections. (NUSCO

l -QSD) 2.1.17 imSCO Procurement Encineerina a) Interface with the Project Engineer and-Plant Engineer for technical and quality requirements of material, equipment, parts and services, b) Review and approve all quality related pur-

chase requisitions.

2.2 Desian 2.2.1 NUSCO Electrical Desi2D a) Provide the design and drafting for the preparation and revision of one-line, sche-Icatic, wiring, panel layout, and equipment arrangement drawings.

b) Provide the design and drafting for the preparation'and revision of loop and logic

~ diagrams.

c) Prepare and issue cable and conduit sched-ules,. duct and trench plans, and raceway

' plans.

'd) Prepare and issue the Electrical Materials L3?t. ,

2 TBS 4P.07M i e J

,.c. _.-n--.. _nme , . - - - , -?* - .n

. I

) " " " *

PAOL PRostCT A88 GNuBNT NQ, R[( NQ.

i 17 o,81 90-013 0 Northeast Utilities Service Company i

NUCLEAR ENQlNEERING & OPERATIONS f

PROJECT DESCRIPTION ;

L i j PAostCT fif 65 l DRAFT CONNECTICUT YANKEE ;

MODERNIZE FEEDWATER CONTROL emostet i

j e) Review and comment on vendor drawings.

7

- f) Incorporate vendor drawings into the NUSCO system.

! g) Prepare and issue the electrical av Juilt drawings. >

h) Provide outage support to facilitate the i installation of cable and electrical equip-ment.

I 2.2.2 NUsco civil & Mechanical Desian (PSD)

a) Prepare Civil _ design calculations, b) Provide the design'and drafting-for the -

i preparation and revision of equipment, con-duit, cable tray, and tubing support draw-ings.

. c) Prepare and issue the' Civil Structural Mate- 0 2 rial List or provide material-ir. formation on the Civil Drawings.

-i d) Incorporate and issue'the Civil as-built '

drawings.

e) Provide outage support to facilitate'the i- - installation of equipment and instrument tubing._ ,

f) Prepare _ Mechanical design: calculations,

~

g) -Provide the design and-drafting for;the preparation-and revision.of Mechanical P&ID, and isometric drawings.

. o

[2TB54P.07M A

y s y4 *s - ,. ,g ,- ~ men

PAQt. PROJECT AlliGNMtNT NO. m g y. NO, 18 o,81 90-013 0 l

Northeast Utilltles service Company NUCLEAR ENGINEERING & OPERATIONS 1 PROJECT DESCRIPTION j PhostCT fiTLE

DRAFT

' CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL TETJCt I

h) Prepara and issue the Mechanical Material List.

1) Prepare and issue the Mechanical as-built-2 drawings.

j). Provide outage support to fac111 tate the j installation-of instrument tubing.

2. 3 Imniement at ion l 2.3.1 NUsco Generation construction i a) Review and comment on the project schedule.

b) Review, comment and approve the project

construction budget.

c) Transport and install instrumentation cabi-4 nets in the Main Control Room.

d) Install new conduit and supports and pull-:

cables in the Turbine Building and Switch-gear Room A.

e) Install'new conduit and supports and coordi-nate with Generation-Test to pull new cables i

in the Main Control Room.

a f) Install new transmitter racks and mounts, g) F.ount new transmitters.

h) Install conduit and supports and pull.new cables in the containment outer annulus, i) Terminate cables on new equipment, j) Install instrument tubing and supports.'

2Tes4P.0?M

... - . . - - . - .. . . . - . . . . . ~ , , , .-.. +- - .

'""'*" ny wo.

pgs emosiefasguygfso.

3 Northeast Utilities service Company NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION PhostCTfiTLE DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL emostcf k) Transport and install new inverters and back-up transformers in Switchgear Room A.

1)- Install / repair fire seals.

m) Purchase field materials.

n) Prepare as-built drawings and transmit them to the Plant Engineer.

2.3.2 NUSCO Generation Test a) Review and comment on the project installa-tion specifications.

b) Coordinate with Generation Construction-to pull and terminate all field side cabling in the Main Control Room, c) Perform modifications to the Main Control Board (component installations,. internal' board wiring).

d) Prepara as-built drawings and transmit them to the Plant Engineer, e) Verify the continuity and arrangement of all- '

" field side" wiring, g) Provide-input'for.the preparation and;updat-ing!of the project schedule, h ) -- Perform all testing l associated with the'new __

inverters'.

I 2.3.3 CYAPCO Instrumentation and Controls a) Review and-comment'on the project'insta,lla-tion. specifications.

2 TBS 4P.07N-

't

. s PAGE PROstCT AS N EN NO. p r NO, Northeast Utilities Service Company NUCLEAR ENolNEERING & OPERATIONS PROJECT DESCRIPTION 1

t PmostCT TITLE DRAFT i

i CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL l

PmostCT b) Perform all internal wiring modifications 4 and circuit card rearrangements in the in-f strumentation cabinets. ,

j c) Terminate cabling at all transmitters and ,

containment penetrations, d) Verify the continuity and arrangement of all j " cabinet side

wiring.-

4 e) Review and comment on preoperational testing d procedures.

f) Perform all I&C preoperational testing pro-

! cedures.

g) Support the integrated operability testing.

h) Prepare as-built drawings and transmit- them to the Plant Engineer. .

1) Provide input for'the-preparation and.updat-i 'ing of the project schedule.

j) Generate reports for new stockcoded spare parts and advise stores of obsolete spare '

i parts.

j 2.3.4 m pco coerations a) Review an'd comment on.the detailed design..

b) Revise and review-the affected operations-procedures.

c) Support preoperational and integrated test-ing.

2.4 Nuclear Trainina

-2 TBS 4P,07M

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EDMikt CRY t M PAGE PRostCT AlliGNwtNT No. Att ho, I

! 21 e,81 90-013 0

' Northeast Utlllties Service Company NUCLEAR ENGINEERING & OPERATIONS ,

, PROJECT DESCRIPTION

?

n

~PAQstCT14768 l

DRAFT

_i CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL

. Wostcf 1

J 2.4.1 fMSCO Ooerator Trainina ,

a) Modify initial and requalification training

)

programs to incorporate project design j changes.

b) Provide classroom and/or hands-on training l for the plant operators.

2.4.2 IMSCC Technical Trainina j a) Prepare training programs for the operation and testing of added plant equipment.

b) Provide classroom and/or hands-on training i for the plant engineers and technicians.

2.4.3 }mSCO Simulator Technical Succort a) Update the simulator to incorporate applica-4 ble portions of this design. change.

', 2.5 Proiect Manaaement and Administrative Suenort 2.5.1 IMSCO Proiect Coordinator a) Prepare and issue PERC' packages.-

b) Review equipment and construction bids.

' c) Resolve conflicts =between various projects-and organizations.-

3 d) Provide a project plan-to ensure coordina-tion of resources.

2.5.2 NUSCO Cos" Encineerina and Schedulina f PSD)_

e 2 tbs 4P.07M

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i 4 e 2

80H4F3 CI(344 PAGE PRostcTAll:0NWENT NO mit NO.

22 o,81 90-013 0 Northeast Utllities service Company l NUCLEAR ENGINEERING & OPERATIONS j PROJECT DESCRIPTION l J.

! TaostcfuT5:

~

DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL Paostet

. I Prepare and revise project material and

\

a) labor cost estimates, i

b) Monitor, evaluate and report on cost vari-unces.

c) Prepare and revise' project engineering, ;

' design, and installation schedules.

d) Provide input to and coordination of the

outage schedule.

! e) Monitor, evaluate, and report on scheduling variances and critical path items.

2.5.3 NUSCO Purchasinc a) Prepare and issue Purchase' Orders for mate- '

rials and labor.

b) Provide expediting of materials as required.

c) Report the expected delivery dates of equip- '

4 ment if other than the "Date Required' on I the Purchase Requisitions. }

2.5.'4 NUSCO Production Materials Grouc a) Provide expediting of material as required.

3.0 QQNDITIONS AND LIMITATIONS This project shall-be installed, tested, and declared opera-tional prior to the completion.of'the 1993 CY. Refueling Outage. .This project shall request the performance of pre-outage work, to the.. extent allowable by CYAPCO. Engineer-ing and Operations, to ensure that the plant modification is completed within the planned duration of the outage. Pre-cautions shall be taken during the equipment replacement's to

2 TBS 4P.07M

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e .

PAQt I PRQJECT A&&iGWENT hQ.90-013 Mdy h0 23 ,,81

Northeast Utilltles Service Company NUCLEAR EflGINEERING & OPERATl0NS ;

PROJECT DESCRIPTION 4

1 g ~PmQstCT 1:16E DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL

.i PAQstCT ensure that minimum channel operability requirements are adhered to. The Plant Operations sign-off on the AWO's will i

control these requirements.

4.0 REGULATORY REQUIRuwagTS This plant design change shall be performed in accordance

' with 10 CFR 50.59, however, an Unreviewed Safety Question nay be involved based on the NRC's interpretations of the rule with regard to safety-related analog-to-digital conver-sions.

The following ISAP Topics are associated with the change:

1 ISAP Topic No. 1.21 - Regulatory Guide 1.97 Instrumentation ISAP Topic No. 1.30 - Reactor Protection System Isolation ISAP Topic No. 1,54 - Safety Implications of Control Systems ISAP Topic No. 1.101 - Steam Generator Overfill Protection ISAP Topic No. 2.04 - Modernize Reactor Protection and i Control Systems 5.0 DESIGN 5.1 Bases of Current Desian >

5.1.1 Feedwater Control Syst2B The Feedwater System is designed to:

2 1)' Provide sufficient flow (approximately 7,600,000 lbs/hr) to the steam generators to extract heat from the reactor coolant and generate steam for power. generation.

2) Perform the system: safety function of con-tainment isolation under accident conditions.-

1-r 2TDS4P.07M 4 -

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4 PAGE PROJECT A56iOWENT NO,

24 ,,81 90-013 R5v NO. ,

Northeast Utilities Senrice Company !

i NUCLEAR ENolNEERING & OPERATIONS PROJECT DESCRIPTION PROJECT TITAL DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL j

^

PA04tCT

! 3) Be capable of isolating components, subsys-tems, or piping if required so that the system safety function will be maintained.

4) Provide for functional testing of the system and components to ensure structural integri-ty and leak tightness, operability and per-formance of active components, and capabili-- ,

ty of the integrated system to function as intended during normali shutdown, and acci-

1. dont conditions.

5) Periodically test the operability of the.

l isolation valves and associated apparatus. .

4 i The feedwater flow to the steam generator is controlled using steam. flow as a demand signal

! for feedwater flow. A trimming action is achieved by measuring' steam generator level and -

by modifying-the level signal with a level con-troller. The level signal adds or subtracts from the feedwater flow signal'to produce adjustments in the feedwater flow and to maintain proper steam generator level.

Note: The following design description '

describes the operation of the 4

Feedwater Control System for Reactor Coolant Loop 1. The operation:of-Loops 2, 3, and 4 is similar.

Steam Flow The primary flow element- for the measurement of steam flow is the Dall flow tube (FE-1201-1).-

This compact flow section provides:the lowest possible head loss in flow measurements.where a:

high differential must be developed, g

' 2 TBS 4P.07M-

PAGE PROJECT AlliGWENi ko. R t v. No 25o,81 90-013 0 Northeast Utilities Service Company NUCLEAR EN0lNEERING & OPERATIONS PROJECT DESCRIPTION PA0stC1111LE DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL PAOJLC1 The differential pressure developed at the flow section for steam flow of zero pounds per hour and 2,500,000 pounds per hour are 0" W.C. to ,

574" W.C., respectively.

A Hagan Ring Balance flow and pressure indicat-ing and integrating transmitter-(FT-1201-1),

provided with a three-valve manifold, measures ;

steam flow as a= function of differential pres-sure across the Dall flow tube (FE-1201-1).

This transmitter also receives a direct steam pressure signal for flow compensation.

The transmitter (FT-1201-1) performs five essen-tial functions: 1) It extracts the square root of the differential pressure signal to yield a

.ignal' linear with flow rate; 2) this linear flow signal is indicated; 3) this linear flow signal is multiplied by a correction factor that is a function of steam. pressure, correcting steam flow for density changes caused by pres-sure variations; 4) the pressure. compensated linearized flow is indicated; 5) the steam pres-sure-is indicated. The:+1 VDC to +9 VDC output of the transmitter (FT-1201-1) corresponds to a

'true steam flow of 0 pounds-per hour to-2,500,000 pounds per hour for 0" W.C. to 574" W.C.

The pressure-compensated linearized output sig-nal is transmitted:- 1) to the feedwater flow controller; 2)-to one pen of the Taylor steam and feedwater. flow recorder FR-1201-1/1301-1);

-and 3) to a voltage sensitive relay.

The function of the feedwater controller will be- i reviewed later.=

9 2 TBS 4P.07M

- ~ - - - - -

. . i

'""C'"'* paot mos CT assiowest so. nev uo. !'

26o,81 90-013 0

~

Northeast Utilities servles Company 1 NUCLEAR ENGINE 5 MING & OPERATIONS 4

PROJECT DESCRIPTION MostCT TITLE DRAFT CONNECTICUT YANKEE l

' MODERNIZE FEEDWATER CONTROL 4

MostCT i

The voltage sensitive relay is considered as part of the nuclear plant, interlocks and is i described in that section.

Feedwater Flow q

The primary element for the measuremant of feedwater flow is an orifice installed in a flow section (FE-1301-1) mounted in the feedwater line. The orifice develops a differential pres-sure of 0" W.C. to'530" W.C. for feedwater flow of 0 pounds per hour to 2,500,000 pounds per-hour,-respectively.

" A Hagan Ring Balance flow indicating and inte-grating transmitter (FT-1301-1A), provided with a three-valve manifold, measures the feedwater flow as a function-of differential pressure across the orifice (FE-1301-1). This transmit-ter perform?.three functions: 1) it extracts the square root of the differential pressure to linearize the feedwater flow signal; 2) it indi--

cates the feedwater flow rate; and 3) it inte-grates the linearized feedwater flow signal.

The linearized output signaloof +1 VDC to +9 VDC corresponds to a flow range of 0 pounds per hour to 2,500,000 pounds per-hour for a differ-ential of 0' W.C. to 530' W.C., respectively.

The linearized output is transmitted tot 1) the feedwater flow controller; 2) the second pen of-the Taylor steam and feedwater flow recorder 4 (FR-1201-1/1301-1); and 3) a voltage sensitive relay..

The function of the feedwater controller wi31 be reviewed later, r.

2TDstr.07N

. = . . . . - . . . , _ ~ , . , , , . - . . _ . . . ,,. ..

4 4 Pa05 PmostCT AlltGWINT NQ RE V. h0 27 ,,81 90-013 0 Northeast utilities Service company !

NUCLEAR ENGINEERING & OPERATIONE PROJECT DESCRIPTICH4

~PAQstCT T176:

UE CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL i

PaostCt The voltage sensitive relay is considered as ,

- part of the nuclear plant interlocks and is i described in that section. I I

Steam Generator Harrow-Rance Level 3

The steam generator level is measured by a nar-row range level transmitter (LT-1301-1) provided

, with a three valve manifold. A signal of 4 to 20 mA is converted to a signal of +1 VDC to +9 VDC. This signal of +1 VDC to +9 VDC represents 0% to 100% of level, respectively. These values correspond to differentials of 85* W.C. and O' W.C., respectively, at 675 psig (501.4'F).

The output signal is trancmitted tor 1) the-

) input filter built into the_ steam generator level controller; 2) the Taylor narrow range-level recorder (LR-1301-1); and 3) a voltage

! sensitive relay (LA-1301-1).

The input filter is a passive network designed to minimize transient noise in the signal to the level controller. The filter unit is~ packaged in the level controller. The time constant for r -the filter in continuously adjustable. ,

The Taylor narrow range level recorder (LR-1301-1) is mounted on the Main Control Board. "The scale rsnge for a +1 VDC to a +9 VDC.

is 0 to'100%, which represents 85* W.C. and O' '

W.C.,-respectively..

The voltage sensitive ~ relay (LA-1301-1) is con-sidered part of the~ nuclear plant. interlocks and.

is described in that section.

The filtered measured level' signal-leLeompared

'- in the steam generator level centroller with the 2 TBS 4P,07H ,

. e EDHekt Aff.844 PAGE PmDJECT AlliGNMENT '.O. Arv No,

28 ,,81 90-013 0 Northeest Utilities Service Company i NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION a

PhostCT fif tt DRAFT l

CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL ,

PhostCT level setpoint signal originating at the setpoint potentiometer of the feedwater manual control station. The feedwater manual control i station is mounted on the main control board. '

l.

The steam generator level controller-is an ad-juntable proportional plus reset controller. In-the steady state condition, the mecsured level is equal to the )evel setpoint and the output of the level contro.ler will be a nominal -5 VDC.

Any variation in measured level, either above er below the setpoint, will cause the output of the controller to increase or decrease. - An increase in level will result in the feedwater control valve re-positioning.toward:the closed position

to reduce the feedwater flow. A d? crease.in the ,

lev 11 has tl.e opposite effect.

Feedwater Flow Controller and Manual Fiow Con-trol Station The feedwater flow controller compares the steam flow signal with the combined feedwater flow and._

level signal. The steam' flow-signal acts as the setpoint for feedwater flow Any error-between the steam flow signal and the combined-feedwater f3ow and level-signal will cause the-flow con-

' troller-to generate a proportional _plus. reset output signal-to open or close the feedwater

valve (FCV-1301-1) to correct the error between i signals.

-If-the steam generator level signal is above the.

~

setpoint, the normal -5 VDC. signal received from the steam generator level-controller will in-crease.- This will raise the combined feedwater.

flow and-level signal,-and if greater.-than~the steam flow signal, will__cause the feedwater valve (FCV-1301-1) to.re-position toward;the i

2TB54P 07M

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- - . . - - . . ~ . - . . . ~ _ ~ - _ - . . - ~ . - . . . . .- .- - - - . . - ~ - .

1 . .

4 :

PAOL PmostCT Atl:0NMt41 No. miivo, f y o,81 _

90-011 0 Northeast Utilltles Service Company NUCLEAR ENGINEERING & OPERATIONS j

, PROJECT DESCRIPTION 1

~~

TAQsf CT TITLE l DRAFT CONNECTICUT YANKEE MODETJ41ZO FCEDWATER CONTROL Paostcf

1 closed position. The feedwater demand signal 10 i transmitted through the manual flow control #

! station (FC-1301-1) to the' Fisher electro-pneumatic (E/P, converter mounted at the F0edwater control valve (FCV-1301-1).

l i-If the steam generator level is below the setpoint, the nor nel -5 VDC signal will decrease and the reverse of the above described action will occur. ,

i

' The feedwater manual flow station (FC-1301-1) is a panel mounted controller which provides t.he operator with a remote mLnual means of regulat-ing feedwater flow. When this station is set to

' ' Automatic' (A), the signal from the feedwater

' flow controller is connected directly to the E/P

converter. The manual flow control station out-put is indicated on the upper meter of the sta-tion. When the station is set to " Manual' (M),

4 the signal from the feedwater flow controller is I interrupted and a cignal originating at the manual station is used to position the Feedwcter Control Valve (FCV-1301-1).-

Transfer from " Automatic" (A) to." Manual" (M) is accomplished by: 1) adjusting the manual poten-

> tiometer (MAN) to null the lower indicator of-

~

the manual flow control station and 2) transfer tho manual / automatic (M/A) switch to manual (M).

Transfer from " Manual" to " Automatic *.is accom-plished by one of the following methods:

1 A. To retain the established. steam-generator level controller setpoint proceed as'fol- '

lows:

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_ ..-. _ __._.._ _ __ _ . . _ . ~ _ _ . _ _ . . _ _ _ _ _ _ _ _ ._

Fit $r PmostcT an34ute ho 'at v. No. i 30e,81 90-013 _

0 Northeast Oilllties Service Company i

i NUC1. EAR ENGINF.ERING & OPERATIONS PROJECT D8!SCRIPTl0N ,

I !

mamma - ,

i DRAFT ,

7 CONNECTICUT YANKEE HODERNIZE FEEDWATER CONTROL

"" ^ - ***

I 740Jt ' .T

1) adjust the manual potentiometer (MAh) 3 i to null the lower indicator of the man-

- ual flow control stations: and *

'2) -transfer _the manual / automatic'(M/A) i switch to automatic-(A)T.

t

B ._ To change the es'a: .blished steam generator-level controller setpoint to provide the-manually adjusted valve position as;follows:

l

1) adjust the steam generator level con-troller setpoint.on the manual station

' to-bring the feedwater flow' controller output signal into agreement with the

" manual station output. This is indi-cated by a null-on the lower indicator:

of the manuel station; and-l

}

l' 2) transfer the manual / automatic-(M/A) switch to automatic-(A).

The above= procedures for transferring from~ auto-matic to manual or the reverse assures that the -

transfer is made without a_ sudden changecin feedwater control valve position.

The Fisher-E/P converter converts the +1 VDC to

+9 VDC electrical. signal to a-' corresponding _

pneumatic-output of 6 to 30 psig. The pneumatic signal is then used~to position the-feedwater-control valve (FCV-1301-1). A decreasing' signal will close the-feedwater control 1 valve, while'an increasing-signa) will open'the valve.

The air supply pressure for'the control valve-operation is-reduced.to 32ipsig by a filter-regulator mounted on.the control valve.

e 2 tbs 4P.07M

, ,-,-; - . . - , , ,,a --. , , , , . . - . , , , . - - , . - . , - , ,- - .-

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P40t pnostciATs4NuiNT wo. Et v. No.

31 ,,81 90-013 0 Northpawt utilities sentice Company i i NUCLEAR ENolNdERING & OPERATIONS j PM0 JECT DESCRIPTION i !

I PAcatCT fiTLE DRAFT j CONNECTICUT YANKEE '

] MODERNIZE FEEDWATER CONTROL j- emoatet n

Between the valve positioner and the valve dia-phragm, three solenoids are provided. The sole- -

noid valves provide automatic operation of-the i

feed regulatina valves following a turbine trip .

tot

.1

1) Assist in the-RCS cooldown. ,

2) Prevent over cooling of'the RCS.

3) Prevent overfilling the S/G.

The solenoid valves are mounted on a panel lo- '

cated east of the feed regulating valves. Under solenoid valve SV-1 is ener-nornal conditions,

gized, SV-2 is de-energized, and'SV-3 is ener-gized. This lineup allows the signal air-from I the positioner-to pass directly to the valve.

! After a turbine trip, the solenoid valves oper-L ate to position the feed regulating valve inde-pendently of the positioning signal from the_

three element controller. If the turbine trips

+

and T,, is- above 545'F with the steam generator level below 69%,_ solenoid.. valves'SV-1 and SV-3 will remain energized and SV-2 willLenergize causing a 30'psig air _ signal to replace the air signal comina from_the positioner._.This will '

cause the feed regulating valve to go to the- ,

' full open position. When T , decreases to ,

545'F, SV-1 and SV-3 will de-energize. The feed regulating valve will fully close when the. air:

vents off. SV-2 will be' energized as long as a f

steam generator level is less than 69%.. ;

Nuclear Plant Interlocks The followingl plant interlocks are-provided.by this systems t

NSSNaNN

_ . _ _ . _ . . . - . _ _ _ . _ _ _ . _ _ _ - _ - . . _ _ _ _ _ . _ . _ - ~ . _ . . _ _ _ _ _ . . _ _ _ . - _ _ _ _ .

l

.{

J E096>a Crv.344 PAGE PROJECT A554GNMEM NO pp No. ,

32 ,,81 90-013 0 1 Northeast Utilltles Service company l NUCLEAR ENGINEENING & OPERATIONS .

PROJECT DESCRIPfl0N 1

t, NMifLE i DPAE.T i

CONNECTICUT YANKEE i MODERNIZE FEEDWATER CONTROL M JECT i 1) the voltage sensitive relay receives the

pressure compensated linearized signal from 4

the indicating flow and pressure transmitter '

l

(FT-1201-1) and the linearized signal from '

the indicating feedwater flow transmitter (PT-1301-1A). -The relay is energized as long as the steam flow signal doas not ex-ceed the feedwater flow signal by 2.0 volts, corresponding to flow differential of ;

525,000 pounds per hour. In case a ditfer.- '

ence of 2.0 volts develops the relay is de-energized,-providing the necessary_a3 arm L and safety actuation.sigt.nis for excessive Inismatch between steam and feedwater ficw.

2) the voltage sensitive relay l(LA-1301-1) i receives a signal from the-steam. generator level controller and remains energized an .

long us the signal does not. fall =below n -

fixed value, indicating-low level in the +

steam generator. When the relay is

.de-energized, - the necessary alarm and saf ety actuation signals.for steam concrator low level are provided. ;

Svstem Power Sucolv" ,

The feedwater control system of each". steam: gen-erator is supplied with regulates ll5V, 60 cycle power from an-individual bus.

The-power supplies e.nter each rack at an AC- -

,. -distribution panel. Fusing'ofcthe distribution supply-is provided.at this panel. .-Indicating '1~

fuses are used throughout, except' for these cwatrollers contaihing their own indicating lights.

1 TBS 4h.07M -

2.

- s -, -ee-- va.r - - . , + -:..--... e n s -

PAGE PAQJECT AlliGNMENT ho 33 ,,83 90-013 Rbv ho.

Northeast Utilltles service Company NUCLEAR ENGINEERING & OPERATIONS ,

PROJECT DESCRIPTION

~>mostCT TITLE DRAFT

(

CONNECTICUT YANKEE J MODERNIZE FEEDWATER CONTROL Ta%tet l

The patch board is the central distribution Its point for all other power and signal leads.

functions are: 1) 115 VAC power is distributed to the controller and the power supplies;

2) +/-10 VDC power is distributed as required;.

and 3) signals from instruments or controllers 4

are received and re-distributed as required.

Both primary and backup power supplies are pro-vided so that a loss of a single bus does not result in a loss of automatic feedwater control 1

or a reactor trip. The arrangement is as

- follows:

Stgm Flow. Feed Flow, and Steam Generator barrow-Rance Level Transmitters Loop Primary Supply Backup Supply 1 Vital A, Ckt. 3 Vital D, Ckt. 3 2 Vital B,_Ckt. 3 Vital A, Ckt. 3 3 Vital C, Ckt. 3 ' Vital B, Ckt. 3

!. Vital C, Ckt. 3 4 Vital D, Ckt. 3 Steam Flow / Feed Flow Mismatch Voltaae Sensitiva

}ielays ,

1 Loop Primary Supply Backup Supply 1 Vital A, Ckt'._3 Vital D, Ckt. 3 2 Vital B, Ckt. 3- Vital A, Ckt. 3 3 Vital C, Ckt. 3' Vital B, Ckt. 3 4 Vital D, Ckt' -3 Vital C, Ckt. 3 Steam Flow / Feed Flew Mismatch Slave Relavs-Relay Primary Supply Backup-Supply' FM1 Vital D, Ckt. 3 Vital'C, Ckl. 3-2 tbs 4P.07M i

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1 e .

l 1D3463 f CLV 344 P t y NO. I PAGE PhostCT AlliONutNT NO.

34 ,,81 90-013 0 l Northeast Utilities Service Company NUCLEAR ENolNEERING & OPERATIONS ,

PROJECT DESCRIPTION l

l ThostcT TiTLt I

DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATEh CONTROL PhostCT FM2 Vital C, Ckt. 3 Vital B, Ckt. 3 FM3 Vital B,-Ckt. 3 .

Vital A, Ckt.3 FM4 Vital A, Ckt. 3 Vital D, Ckt. 3 Steam Generator Narrow-Ranae Level Voltaae San-sitive Relavs Loop Primary Supply Backup Supply 1 Vital A, Ckt. 3 Vital D, Ckt. 3 2 Vital B,LCkt. 3 Vital A, Ckt. 3 3 Vital C, Ckt. 3 Vital B, Ckt. 3 4 Vital D, Ckt. 3 Vital C, Ckt. 3 Steam Genergtor? Harrow-rance' Level Slave Relave Relay Primary Supply Backup Supply SGL1 Vital A, Ckt. 3 Vital D, Ckt. 3 SGL2 Vital B, Ckt. 3 Vital A, Ckt. 3 SGL3 Vital C, Ckt. 3 Vital B, Ckt. 3 SGL4 Vital D, Ckt. 3 Vital C, Ckt. 3 Eg h ter Control 10 VD,Q Power Sucolies Loop Primary. Supply Backup Supply ,

1 Vital A, Ckt. 3 Vital D,-Ckt. 3 2 Vital B, Ckt. 3 Vital A, Ckt.-3 3 Vital.C, Ckt. 3 Vital B, Ckt. 3 4 Vital D, Ckt. 3 Vital C, Ckt. 3 Feed Reaulatina Valve Solenoids SV-1, SV-2,_

SV-3 All twelve powered from Semi-Vital Bus 2.

5.1.2 Steam Flow /Feedwater Flow Mismatch Reactor Trio 2 TBS 4P.07M

_ _ - . . ...____._-m ._.._.m.. . - _ _ . . _ - . .

. _ . . _ . - m . m .- . _ _ _ - _

EDH8M CEV t N PAOL PR0sicf Alli4NMENT NO REW NO. '

35 o,81 90-013 0

. Northeast Utilltles service Company NUCl.EAM EN0lNEERING & OPERATIONS .,

PROJECT DESCRIPTION I

1 Papstet Tau DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL Pnostet 4

l A potential loss of. heat sink due to loss of i water inventory in the steam generator can be i recognized in advance if steam flow rates exceed feedwater flow rates. To reduce the loss of steam generator inventory, a reactor trip is provided on coincident signals of large steam 1

flow /feedwater flow mismatch and low steam gen--

i erator water level for any one of the four steam generators.

This trip channel uses the flow signals for main steam and feedwater sensed by the_ steam genera-3 tor level control system for each steam genera-

! tor. The steam flow signal for each loop is i compared to the feedwater flow signal for the same-loop.

If steam flow exceeds feedwater flow by-more 1 than 20% of the mass flow rate for full power steam demand, an alarm will sound. If.the steam-generator' level, as indicated by the narrow-e range level transmitter in the same loop, is 10%

! or below, an alarm will sound. Any of-the four loops will produce a reactor trip if these two i

conditions simultaneously. occur in.a given loop. -

i 5.1.3 steam Line Break Reactor Trio ,

i Excessive steam f1ow will cool the RCS and in-sort positive reactivity because:the temperature coefficient is negative. For this reason a two-out-of-four. logic.is set up to trip the reactor-on steam flow greater than 110% of full power steam flow. Steam flow in each~of the four main steam lines is sensed as a pressure differential

.across elbow taps located'in the first 90 degree elbow outside the reactor-containment. This

-signal is sent to a meter relay bistable in the control room, where a trip signal is initia6ed 2TSS4P.07M- ,

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

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

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l i

' '*"C"* ,An

, 0-013 36 ,,81 enos CT nhinwisiso. n5t wo.

Northeast Utilltles Service Company J NUCLEAR ENGINEERING & OPERATIONS r

PROJECT DESCRIPTION i

4 P40stCT T4TLt DRAFT

. CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL phostCT and all main steam trip valves close, if two channel setpoints are exceeded. A large steam line break upstream of these pressure tapc will

I trip the reactor through either high flux or low

! pressure reactor trip.

1

. A reactor trip will also occur if the-lower limit switch on any of the main steam trip valves indicate closure of the va?ve. This trip 1 is inactive below 10% (P7)' power.

5.1.4 Steam Generator overfill Protection ,

l Each Steam Generator has two wide-range level

- transmitters (LT-1302-1A, - 1B, - 2A, -2B, -3A, i -3B, -4A, -4B). Steam Generator overfill pro-j cection is. initiated if either wide-range level

~

transmitter senses a 69% high level condition.

1 This-one-out-of-two initiation logic will then isolate sain feedwater by closing the main feedwater regulating valves.

5.1.5 Vital Inverters A and B The Train A Channels A and B 120 V vital AC power system consists of two 3 kVA invertere-- '

Inverter A and Inverter B. They are located in Switchgear Room A on-the same rack with aban-doned Inverters C and D which were-replaced with new ones located in Switchgear-Room B.

The 125 VDC-input is: supplied to the inverters- ,

from DC-BUS-A Circuits 8 and 20.

The 120-VAC regulated outputs of Inverters A and a B are supplied to 120.VAC vital Buses'A and B, respectively, in the main' control: board. The supply from the inverters can-be aligned such=

thatLInverter.A can also~ supply Vital Bus B,' and 2Testr.07M 6

>y- y n e gi , ,,r-+r y er

(D3463 2 CtV.t 64 PA0t PhostCT AlliGNMcNT NO. Rev No.

37 o,81 90-013 '

0 Northeast Utilities Service Company NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION-PmostctTi1LE DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL emostet Inverter-B can also supply Vital Bus A. The cross-connect is performed' manually and doing so-places the plant in a technical specification action item (TS- 3/4.3.8.3.1). Also, due to existing load constraints on Inverters A and B,-

some loads must be manually shed in order to utilize this alignment (per CY procedure AOP 3.2-15, " Loss of Vital Bus" ) .

External cooling fans are installed underneath the inverters to supply cooling to interior.

components. The power source for this circuit is panel LP-Cl-1A.

An annunciator on the main control board signi-

fies loss of voltage on a vital bus.

5.2 Method of Chance 5.2.1 E. tap.n Generator' Feedwater Flow = Transmit ter a) Install a-transmitter rack.in thu Turbine Ouilding-(El.-21'6") near the existing Steam

. Generator feedwater' flow transmitter rack.

b) Install-new; instrument tubing-tcythe'new instrument rack.i. >

c) Mount eight:4-20 mA, Class'1E' Steam Genera-tor feedwater flow transmitters,-FT-1301-1B,

-1C, -2B,--2C, -3B, -3D,. -4B,'and -4D on.the-new transmittertrack.

. d) . Connect the new-tubing to FT-1301-1B ando FT-1301-1C.: Install independent. valving tof each transmitter, e-L

!K 2Tes4P.07M ,

y-- i ,.

- - i

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e .

I EDM6F2 REV12 N '

PAGE PROJECT AlliONMENT No. REv, No.

38 o,81 90-013 0-Northeast Utilities Service Company NUCLEAR ENGINEERING & OPERATIONS '

PROJECT DESCRIPTION PROJECT TITLE DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL PROJECT e) Connect the new tubing to FT-1301-2B and FT-1301-2C. -Install independent valving to

each transmitter.

f) Connect-the new tubing.to FT-1301-3B and-FT-1301-3D. . Install independent valving to 1 each transmitter.

I g) Connect'the new tubing _to FT-1301-4 Brand-FT-1301-4D.- Install independent valvingito each transmitter, h) Install channel segregated raceway and cable

.from the new. transmitters to the Main Con-trol Room for Channels C and D. Use existing cable.and raceway for Channel B.

i) Install Main Control Room circuitry, cable, and wire.

j) Perform continuity tests and' terminate all :

cable and wire. .

k) Energize, test, and calibrate the' equipment.

1)' Remove the old Steam Generator feedwater flow transmitters and associated-hardware.-

S.2.2 Steam Generator Steam Flow Transmitters i

a) Install a1 transmitter rack:in the Turbine Buildingf(El. 37'6"):near'.the existing _ Steam 1

Generator steam flow transmitter rack, b) Install.new instrument-tubing to the new s

instrument rack.

c) Mount eight 4-20 mA, Class-1E. Steam Gen, era--

tor Steam flow' transmitters, FT-1201-1B, 2 TBS 4P 07M J

t .

ED3443 2 REV 2 44 R[tf NO.

PAGE. PROJECT A$$10NMENT NO.

39 e,81 90-013 0 Northeast Utilities Service Company NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION PmostCT14TLE DRAFT CONNECTICUT YANKEE

- MODERNIZE FEEDWATER CONTROL PAQstCT and -4D on the

-1C, -2B, -2C, -3B, -3D, -4B, 1

new transmitter-rack.

d) Connect the new tubing to FT-1201-1B and FT-1201-1C. Install independent valving to each transmitter.

e) Connect the new tubing to FT-1201-2B and FT-1201-2C, Install independent valving to each transmitter.

I f) Connect the new tubing to FT-1201-3B and 1 FT-1201-3D. Install independent valving to each transmitter, g) Connect the new tubing to FT-1201-4B and FT-1201-4D. Install independent valving to-

+ each transmitter.

! h) Install channel segregated raceway and cab 1'e from the new transmitters to the Main Con-

^

trol Room for Channels C and D..Use existing cable and raceway for Channel B.

i) Install Main Control Room circuitry, cable, and. wire.

j). Perform continuity tests and terminate all cable and' wire.

k) Energize, test, and calibrate the equipment.

1) Remove the old Steam. Generator steam flow transmitters and associated hardware.

-5.2,3 Steam Generator Narrow-Rance Level Transmitters a) Seismically install two dual transmitte,r- l

' mounts near-each existing Steam Generator ~ 1 2 TBS 4F.07M l

1

-- 4 I

PAQt PROJECT AS5iGNMENT NO. Rtv. NO, 1 40 e,81 90-013 0 I Northeast Utilities Service Company NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION i

PA0 JECT TITLt DRAFT CONNECTICUT YANKEE-MODERNIZE FEEDWATER CONTROL

emostct narrow-range level trans: itter LT-1301-1, and -4 at the mis level of the Con-4

-2, -3, tainment outer annulus.-

4 b) Seismically extend the instrument tubing for LT-1301-1, -2, -3,-and -4 to the two new transmitter mounts.

c) Seismically mount one 4-20 mA, . Class 1E Steam-Generator narrow-range level-transmit-ter on one of the'new dual transmitter mounts at each location. Install LT-1301-1A-on Loop 1; LT-1301-2A on Loop 2; LT-1301-3A on Loop 3; and LT-1301-4A on Loop.4.

d) Seismically mount two 4-20 mA, Class 1E

' Steam Generator narrow-range level transmit-ters on the other dual transmitter mount.

Install LT-1301-1C-and LT-1301-1D on-Loop 1; -

LT-1301-2C and LT-1301-2D on Loop 2;;

LT-1301-3C and LT-1301-3D on Loop 3; and' LT-1301-4C and LT-1301-4D on Loop 4, e) Connect the extended tubing from LT-1301-1 to LT-1301-1A,' LT-1301-1C, and LT-1301-1D.

Install independent valving to each trans-mitter.

f) Connect the extended tubing from LT-1301-2 to LT-1301-2A, LT-1301-20, and LT-1301-2D'.

Install independent' valving to each trans-mitter, g) Connect the extended tubing from LT-1301-3 to LT-1301-3A, LT-1301-3C,-and LT-1301-3D.

Install-independent valving to each trans-

- mitter.

2 TBS 4P,07M

1

.- . 1 PAGE PAOJECT A$$iGNMENT NO. M E V. NO, 1 41o,81 90-013 0 Northeast Utilltles Service Company ;

NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION pmoJECT T4TLE 3

DRAFT CONNECTICUT YANKEE-MODERNIZE FEEDWATER CONTROL PROJECT h) Connect the extended tubing,from LT-1301-4 4

to LT-1301-4A, LT-1301-4C, and LT-1301-4D.

Install independent' valving to each trans-mitter.

i) Seismically install channel-segregated con-duit and cable from the new transmitters to the Containment penetrations, j) Use spare cable from-PA 83-117 from-:the Cable Vault to the Main Control Room.

4 k) -Install Main Control Room circuitry, cable, and wire.

1) Perform continuity tests and terminate all cable and wire.

m) Energize, test, and calibrete the equipment.

n) Remove the old Steam Generator. Narrow Range-Level transmitters and associated hardware.

5.2.4 Steam Line' Break Flow Transmitters a) Seismically mount four 4-20'mA, Class 1E Steam Line flow transmitters.in place of existing flow transmitters FT-1202-1, -2,

-3, and -4 in the Protective Enclosures, b) Seismically extend and connect existing-tubing and. independent valving to_each transmitter.

c) Utilize existing field cabling.

d) Install ~ Main. Control Room' circuitry, cable,.

and wire. ,

1 l

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1 Ec u n t cEv.s u PAGE PROJECT AS$tGNMENT NO. mit No.

42 o,81 90-013 0 Northeast Utilities Service Company NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION i

PROJECT 14TLE DRAFT-CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL i PROJECT e) Perform continuity tests and terminate all cable and wire.

f) L4ergize, test, and_ calibrate. equipment, g) Remove the old Steam Line Break Flow trans-mitters and-associated hardware.

5.2.5 Steam Generator Pre'ssure Transmitters 4

a)- Seismically mount four 4-20_mA, Class 1E Steam Generator pressure. transmitters in place of existing containment mounted pres-2 sure transmitters _PT 1201-1, -2, -3,.and.-4.

+

Relab13 the new transmitters as-PT 1201-1B, a

-2B, -3B, and -4B. Utilize the spare mounts beside the Train A Steam Generator narrow-

~

range level transmitters.

b) Relable-the existing' Steam Generator pres-sure transmitters.(PT.1201'-1B, -2B,--3B, and

-4B)" mounted in the Terry Turbine-Building 9 as PT 1201-1C, -2C, -3D, andL-4D.

.c) Seismically extend and connect existing-tubing and independent' valving to each' transmitter.

d) . Utilize existing field cabling.

d) Install Main Control Room circuitry, cable, and wire.

e). Perform continuity-tests and terminate all

-cable and-wire, f) Energize, test, and calibrate equipment.

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ED34652 CEV,844 .

PAGE PROJECT A8640NMENT NO. REE NO. ~,

43 o,81 90-013 0 Northeast Utilities Service Company NUCLEAR ENGINEERING & OPERATIONS

. PROJECT DESCRIPTION PA0 JECT TITLE DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL

, PROJECT i

g) Remove the old containment mounted Steam Generator pressure transmitters and associ-ated hardware.

l 5.2.6 ' Main control-Room Instrumentation Cabinets 4

a) Seismically install the two new two-bay Feedwater Protection instrumentation cabi-nets behind the Main Control Board, b) Remove the existing Hagan Feedwater Control

-System instrumentation cabinets in'the rear of Main Control Board D-E.

c) Seismically install the two-new single-bay '

8 Feedwater Control System instrumentation cabinets'in the-rear of Main Control Board D-E.

d) ' Connect wiring from existing Foxboro cabi-nets _"NB" and "NS" for bypass. flow input to Feedwater' Control System utilizing existing

-spare cable, e) Wire existing spare-steam / feed flow mi'smatch logic-to-contact. relays'in Reactor Trip Logic cabinets to plant annunciator and computer.

- f) Remove existing contact-to-logic cards for Steam Line Break inputs _and add new logic-to-contact relays in: Reactor Trip Logic _-

cabinets to plant annunciator and computer, g) Terminate _all-field cable.and wire _at the new Feedwater Control System instrumentation cabinets.

h) Energize, test, and calibrate _ the equip $nent, i~

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asm CESw PAGE PROJECT AEliONMENT NO. ret No.

44 e,81 90-013 0 Northeast Utilities Service Company NUCLEAR ENGINEERING & OPERATIONS r

PROJECT DESCRIPT!ON PA0 JECT TITLE DRAFT-CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL-PAOJECT 5.2.7 Main control Board Modifications a) Remove obsolete Main Control Board equipment and move existing equipment as necessary.

b) - Seismically mount replacement and additional Main Control Board equipment.-

c) Install Main Control Board cable and wirei d) Perform continuity tests 3nd_ terminate all cable and wire, e) Energize, testi and calibrate'the. equipment.

5.2.8 Vital Inverters A and B a) _The new vital power suppli'es-are specified to be as identical as possible to that of:

Inverters C and D. As-such,- the new-arrangement'will consist of two inverter cabinets and two constant' voltage transform--

ers which are.used as an alternate source.

b) Existing Inverters A and B.will.be electri-cally disconnected. Existing field' cables-will be re-utilized _to the best_ extent possible, c) The external cooling fans will be deenergized'and: removed. _The circuit will be disconnected at' Panel LP-Cl-1A. The new-inverters-have internally powered cooling fans.

d). Existing Inverters A and,B, abandoned:

c L Inverters C and D, and their. associated l mounting rack will be physically remove,d.

l The new inverter cabinets and constant volt-

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EDN6F2 CtY 244 REv NO, PAOL PROJECT A$3tGNMENT No.

45 o,81 90-013 0 Northeast Utilities Service Company NUCLEAR ENGINEERING & OPERATIONS-PROJECT DESCRIPTION PROJECT f att.E DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL PROJECT age transformers will be located in this area. The inverter cabinets will be floor mounted. The constant voltage transformers will be attached to a floor-mounted rack, e) The DC input.to the' inverters will still be from DC-BUS-A. The. existing circuit. break-ers will be used and the input cables will be re-utilized to the best extent practical.

f) Two new circuits will be' required from MCC-13 to supply input-to the alternate source constant voltage transformers.

g) New control cable and raceway will be added from the inverters to the main control board annunciator to signify inverter trouble.

5.3 Desian Inouts l 5.3.1 American National Standards Institute a)- ANSI N45.2, 1977 Quality Assurance Pro-gram Requirements-for

Nuclear Power Plants Packaging,.-Shipping,-

b) ANSI.N45.2.2, 1972

' Receiving, Storage, and~

Handling of Items for

-Nuclear ~ Power plants c) ANSI C39.1, 1981- ' Requirements for Elec-trical Analog Indicat-ing Instruments d) . ANSI C39.2,'1964' Direct Acting Electri- )

cal Recording.Instru-ments. ,

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ED W W M PAGE PROJECT AS$4GNMENT NO. REV,NO.

46 o,81 90-013 0 Northeast Utilltles Service Company NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION PROJECT TITLE DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL PROJECT e) ANSI C39.5, 1974 Safety Requirements for -

Electrical and Elec-tronic Measuring.and Controlling Instrumen-

.tation-.

f) ' ANSI /IEEE-ANS-7.4.3.2, 1982 Application Criteria for Programmable' Digi-tal Computer. Systems and Safety Systems of Nuclear Power Gener-

ating Stations.

g) ANSI /IEEE 741~-90 Standard Criteria for the Protection of Class 1E Power Systems and Equipment in Nucle ,

ar Power-' Generating Stations.

5.3.2 American society-for Testino and Materials a) ASTM A262,1986 . Recommended' Practice for Detecting 1 Susceptibility to Inter-granular Attack in '

Stainless ~ Steels.

I b) ASTM A380',_.1978 Recommended Practice for De-scaling andLCleaning Stainless Steel Surfaces.

5.3.3 Institute of E]ectrical and' Electronic Enaineers a). IEEE 279, 1971 Criteria'for Protection-Systens for ' Nuclear Power Generating Stations.

r-

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t E83443-2 Cry 344 RE% NO, PAGE PROJECT AS$tGNMENT NO.

4- 47 o,81 90-013 0 Northeast Utilltles Service Company 1 NUCLEAR ENGINEERING & OPERATIONS '

PROJECT DESCRIPTION.

PROJECT TITLE DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL PROJECT b) .IEEE 308, 1980 Criteria for Class-1E Power Systems for Nuclear Power-

+

Generating Stations.

c) IEEE 317, 1983 Electric' Penetration Assem-l blies in Containment Struc-

! tures for Nuclear Power

' Generating Stations, d) IEEE 323, 1974 Standard for Qualifying-Class 1E-Equipment,for Nu-clear Power Generating Sta-tions.

e) IEEE 338, 1977 Criteria for~ Periodic Test-ing.of Nuclear Power Gener-ating Station. Safety Sys-tems.

f) IEEE 344, 1975 Trial Use Guide for Seismic

Qualification of Class 1E Electrical Equipment for Nuclear Power Generating Stations.

g) IEEE 336, 1985 Standard Installation, In -

spection and Testing Requirements for Power,.In- -

strumentation,.:and Control Equipment at Nuclear Facil-ities.

.h) IEEE 379, 1977' Application of the' Single-Failure Criterion =to Nucle-

' ar PowerLGenerating Station i Class 1E Systems.

'i) IEEE 381,.1977 Criteria for Type Testp of Class 1E Modules Used'in 2 TBS 4P.07M

PAGE - PROJtOT A$$10NMENT NO.

48 ,,81 90-013 R$U. NO.

Northeast Utilities Service Company NUCLEAR ENGINEERING & OPERATIONS

, PROJECT DESCRIPTION PROJECT TITu DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL PROJECT Nuclear Power Generating

, Stations.

j) IEEE 383, 1974_ Standard for Type Test of i

Class 1E Electric Cables; Field Splices and Connec-tions for Nuclear Power Generating Stations.

k) IEEE 384, 1981 Criteria:for Independence of_ Class 1E Equipment and Circuits.

1) IEEE 420, 1982 . Design'and Qualification of Class 1E Control Boards,

' Panels and Racks used in Nuclear Power Generating Stations.

m) IEEE 467, 1980' -Quality Assurance Program Requirements-for'the Design and Manufacture of Class'1E Instrumentation and Elec--

4 trical Equipment for Nucle--

ar Power Generating Stations, n) IEEE 472, 1974 Guide for Surge Withstand Capability (SWC) Tests.

o) IEEE 577, 1976 Requirements for Reliabili-ty Analysis in the Design and. Operation-of Safety Systems for Nuclear Power.

. Generating Stations.

p) IEEE 603, 1980- Criteria for Safety _ Systems-for Nuclear Power Generat- '

ing-Stations.

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rAOL PROJECT A$$10NMENT NQ. Rt y, NO.

49 o,81 013 0 Northeast Utllities Service Company -

NUCLEAR ENGINEERING & OPERATIONS-PROJECT DESCRIPTION PAodEOTTITLE DRAFT CONNECTICUT YANKEE 1

MODERNIZE FEEDWATER CONTROL PROJECT q) IEEE 650, 1979 Standard for Qualification of Class 1E Battery Charg-i ers and Inverters for Nu-clear Power Generating Sta-tions.

' r) IEEE 690, 1984' Design and Installation of Cable Systems for-Class 1E -

Circuits in Nuclear Power Generating Stations.

4 s) ANSI /IEEE-ANS-- Applicati ~ -iteria for 7-4.3.2-1982 Programme (gital-Com-puter Sn n Safety Systems.of h ear: Power l

Generating StL ions.

5.3.4 U.S. Nuclear Reculatorv Commission (NRC)'

a) 10CFR50,' Appendix B Quality-Assurance, Criteria for Nuclear

- Power Plants.

1 e b) 10CFR, Part 21 Reporting of Defects.

i' and Non-compliance.

c) 10CFR50, Appendix R Fire Protection Program

'for Nuclear Power Fa-

cilities Operating

-Prior to January =1, 1979.

d) 10CFR50.49 Environmental-Qualifi-cation of Electric Equipment Important-to Safety for Nuclear-Power Plants.

r i' 2 TBS 4P.07M.

_ma.a 4 J: 4 .

PAGE PAOJECT AS$1GNMENT NO. M(V. NO.

50 o,81 90-013 0 Northeast Utilities Service Company -

NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION 4

PROJECT TITLE DRAFT l CONNECTICUT YANKEE ,

i MODERNIZE FEEDWATER CONTROL PROJECT t

e) 10CFR50.59 Changes, tests and i experiments, f)- R.G. 1.22 Periodic-Testing of Protection System Actu-:

ation Functions.

-g) R.G. 1.29, Rev. 3 Seismic Design Sept. 1978. -Classification.

h) R.G. 1.38, Rev'.- 2 Quality Assurance May 1977 Requirements for Packaging, Shipping, Receiving,. Storage, and Handling _of Items for -

Water-Cooled Nuclear Power Plants.

i)- ' R.G. 1.75,-Rev. 2f Physical Independence Sept. 1978 of. Electrical' Systems.

j) R.G. 1.89, Rev. 1 Environmental

-June 1984 Qualification of Certain Electrical

' Equipment.Important to Safety for. Nuclear Power Plants, k) R.G. 1.97,'Rev. 3 ~ U-S. Regulatory Dec. 1980 Commission Instrumenta-tion for Light-Water-Cooled Nuclear Power.

Plants to Assess Plant-and Environmental Con-ditions_.during and following an accident.-

1) R.G. 1.100, Rev. 1 Seismic lQualificat, ion 2 TBS 4P.07M.

)

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I sosa s nEv.w PAGE PROJECT AS$iGNMENT NO. .

.RES No, .90-013 :n '

51 0'81 .L Northeast Utilities Service Company NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION ,

~ PROJECT T4TLE DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL PROJECT Aug. 1977 of Electric Equipment 4

for Nuclear Power Plants.

m) R.G. l.152 Criteria for-Programmable Digital Nov. 1985 Computer System-Soft-ware in Safety-Related Systems of Nuclear, Power Plants, n) IMREG-0588, Rev. 1 Interim Staff-Position July 1981 on Environmental-Quali-fication of Safety-Related Electrical Equipment.

5.3.5 Instrument Society of America a)- ISA, S67.01, 1979 Transducer and-Trans- -

' mitter Installation for Nuclear. SafetyApplica-tions.

b) ISA,' S67.06, 1984 Response Time-Testing-of Nuclear. Safety-Re-lated Instrument Chan-I nels in Nuclear-Plants.

, 5.3.6 Mechanical Encineerina Standards I a) ASME. Boiler and Pressure Vessel Code, Sec-tion ~III and IX 1983 Edition.up to and in-cluding Winter 1983 Addenda ~.

b) - ASME Boiler and Pressure Vessel Code,: Sec-: .

tion -XI, " Inservice Inspection." 1983 Edi-tion up-to and including the Summer 1984 Addenda.

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e .

PA08 PROJECT AS$1GNMENT NO. aty,No.

52 o,81 90-013 0-Northeast Utilities Service Company NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION -

PROJECT TITLE

~ DRAFT

~

CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL enoJact c) AISC Specification'for the Design, Fabrica-tion, and Erection of Structural Steel for Buildings; 8th Edition.

- d) AWS D1.3, Specification for Welding Sheet Steel and Structures (1981), of latest Edi-tion in effect during' installation.

. e) AWS D1.1, Structural Welding. Code (1984), or Latest Edition in effect during installa-tion.

f) Welder Qualifications per AWS D1.1, AWS Dl.3 and ASME Section IX as applicable, i

. Note: Latest issue of such. specifications, standards, and' codes means'the-issue (including latest published case rul-ing, interpretation, and. addenda) in force on the date of the PDCR. Adop-tion of any subsequent issue'of case rulings-shall.be subject to the owner's-approval.. Northeast Utilities Welding

-Manual referencing earlier additions to the code are acceptable. C. N.-Flagg Welding Manuals referencing earlier additions to the code are acceptable.

5.3.7 Plant Desian Documents /Innuts a) CYAPCO Haddam Neck Station Updated FSAR (May, 1987).

b) NUSCO Nuclear Training Manuals for Connecti-

~

cut Yankee 1S ystems, c) Connecticut- Yankee System Descriptions, Revision 1. ,

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PAGE PROJECT Al$10NMENT NO Riv. NO, 53 o,81 90-013 0 Northeast Utilities Service Company NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION 4

PROJECT TITLE DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL PUOJECT d) Feedwater Control System Description A-4079, Westinghouse Electric Corporation, e) Reactor Control and-Protection System De-scription CYW-300, Westinghouse Electric ,

Corporation.

5.4 Detailed Desian 5.4.1 Procurement Soecifications-a) NUSCO Specification SP-EE-323 establishes-the requirements for instrumentation to replace the Feedwater Control ~ System and secondary-side Reactor-Protection functions.

This instrumentation was purchased-QA.Cate-gory 1, Class lE from the Voxboro Company under Furchase Order 884365. -(Portions'of the Parchase Order are non-QA.)

b) Field transmitters were purchased QA-Catego-

-ry 1, Class lE, from Rosemount Incorporated b under Purchase Order 235030, c) Main Control Board indicators were purchased QA Category 1, Class lE from International Instruments under Purchase Order- 886451.

d) NUSCO-Specification'SP-EE-336 establishes-the requirements for~the Vital Inverters and.

associated hardware. This equipment was purchased QA CategoryL1, Class'1E from

.Cyberex Incorporated under Purchase Order 887440.

e) All new: cable to be installed has been pur-chased QA Category 1 and satisfies the flame retardant requirements of'IEEE 383. ,

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PAOL P gv. NO, 54 o,81 lPDCT 90-013 AS$40NMENT 0No.

Northeast Utilities Service Company i NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION 4

~ PROJECT TITtt DB/ZT CONNECTICUT YANKEE-MODERNIZE FEEDWATER CONTROL rao.act 5.4.2 Defiign Drawinas a) A functional description of this plant de-sign change is provided by drawings listed on drawing index, 16103-31095,- Sheets 1B, 1C, and 1D.'

b) Connection diagrams of all Foxboro. internal cabinet wiring are provided by drawings listed-on drawing index,. 16103-31095, Sheets 1B,~1C, and 1D.

c) The-following loop connection diagrams show the overall instrument channel arrangements and physical layout, including field. inter- ,

connections:

16103-31079, Sh. 37A SG #1 Level & Pressure.

16103-31079, Sh.-37B SG.#1 Steam / Feed Flow &

-SLB 16103-31079, Sh .' 3 8 A - SG #2. Level & Pressure 16103-31079, Sh. 38B SG-#2' Steam / Feed Flow &

SLB 16103-31079, Sh. 39A SG:#3 Level & Pressure 16103-31079, Sh. 39B SG #3 Steam / Feed-Flow &

SLB 16103--31079, Sh.-40A SG'#4' Level &EPressure 16103-31079, Sh. 40B SG-#4 Steam / Feed Flow &

SLB 16103-31079, Sh. 58 -SG #1-4'WR' Level.Ch. A 16103-31079,.Sh. 59' SG #1-4 WR Level Ch. B 16103-31079, Sh. 66 SG Pressure'Ch. C &LD 16103-32150, Sh. 11B Auxiliary Feedwater Flow-di The seismic design and mounting details of equipment installed under this. plant' design change is detailed by the'following app,oved- r design drawings:

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PAOL PROJECT AlsiGNMENT No. . ret No.

55 o,81 90-013- 0 Northeast Utilltles Service Company NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION PhostCT fifLE DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL J PROJECT 16103-28803, Sh. 12A Transmitter Racks Turbine Building 16103-28803, Sh. 12B Transmitter Support Containment 16103-33035, Sh.-25A Spec. 200 Cabinet In-stallation-e) Instrument tubing and valving associated-with thic-plant design change are detailed by the following approved design drawings:

16103-28807, Sh. 1 ISO-Steam' Flow Trans- i mitters FT-1201-1B, 1C, 2B, 2C-16103-28807,-Sh. 2 ISO-Steam Flow Trans- .

mitters FT-1201-3B, 3D, j 4B, 4D 16103-28808, Sh, 1 ISO-Feedwater Flow Transmitters i FT-13 01-1B , - .1C , 2B, 2C 16103-28808, Sh. 2 ISO-Feedwater: Flow.

Transmitters

'FT-1301-3B,13D, 4B,- 4D' ISO-SG-#1 Transmitter 16103-28059, Sh. 9A-LT-1301-1A, 1C, '1D

'16103-28059, Sh. 10A ISO-SG_#2 Transmitter '

LT-1301-2A,-2C,_2D 16103-28059, Sh. 11A ISO-SG #3 Transmitter LT-1301-3A,-3C, 3D 16103-28059, Sh. 12A ISO-SG #4'_ Transmitter LT-1301-4A,_4C, 4D- --

f ) .- Modifications'to the Main Control-. Board equipment levout are detailed by the follow-ing approven' design drawings:

16103-30049,.Sh. 5' MCB Front-View,' Panel:E' 16103-30049,_Sh. 6 MCB' Front View,~ Panel F'

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"PAGE . PROJECT AWGWENT NO.

mE. NO, 56 ,81 90-013 Northeast Utilities service Company NUCLEAR ENGINEERING & OPERATIONS l- PROJECT DESCRIPTION 5 PmostCT T6TLE DRAFT CONNECTICUT YANKEE MODERNIZE FECDWATER CONTROL PROJECT a

16103-30049, Sh. 6A MCB Front View,' Panel F (Bottom)

- 16103-30049, Sh. 7 .MCB Front View, Panel.G (Top) +

16103-30049, Sh. 13 MCB Relay Panels D10 and D11 (Resr) 16103-30049, Sh. 13A MCB Relay Panels D10 and D11 (Rear) 16103-30049, Sh. 14- MCB Relay Panels F7.and

-F8 (Rear) 4 16103-30058, Sh. 2' -MCB Front View Post-Accident Panel FF g) The following drawing transmittal's incorpo-rate this plant design change:

r PSD-DT-630-92 PSD-DT-637-92 PSD-DT-826-92

! PSD-DT-631-92 PSD-DT-742-92

PSD-DT-632-92 .PSD-DT-765-92 PSD-DT-633-92 PSD-DT-769-92 PSD-DT-634-92 PSD-DT-785-92 PSD-DT-635-92 PSD-DT-805-92 5.4.3 Desian Evaluations a) NUSCO ENGINEERING MECHANICS, in conjunction '

with NUSCO CIVIL DESIGN, will perform a-

-Seismic Qualification review and design 4

verification to examine the seismic integri-ty of equipment and' equipment mounting con-t figurations, b) NUSCO ELECTRICAL ENGINEERING (PSD)' will-per- -

form a review and design-verification to examine the impact-lof the change-on existing:

electrical' equipment and.the electrical-characteristics'of the added equipmentnused to implement the plant design ~ change. ,

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4 EDH43 2 REV,344 PAGE Pm0 JECT AS$1GNMENT NO. REv, No.

57 o,81 90-013- 0 Northeast Utilities Service Company NUCLEAR '"NGINEERING & OPERATIONS PROJECT DESCRIPTION 3 PROJECT TITLE DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL i emoJECT 4

c) NUSCO ELECTRICAL ENGINEERING, SPECIAL STUD-IES, will perform a review and design veri-fication to examine the Environmental Quali-fication of equipment purchased to' implement the plant design-change as well as the in-4

- sta31ation of this equipment in harsh envi-ronments.

d) NUSCO I&C ENGINEERING-will perform a review.

and design verification of the-overall change and.the impact of the change on ex -

isting instrumentation and control-equip-i ment, e) NUSCO'PROBABILISTIC RISK ASSESSMENT has performed a review and design. verification-concluding that the plant design change will result in a net reduction in core melt fre-quency.

f) NUSCO RELIABILITY ENGINEERING has performed a reliability analysis for this plant design-change-in accordance with IEEE 577-1976, Requirements-for. Reliability Analysis-in the-Design and Operation of Safety Systems for Nuclear Power Generating Stations.. ,

l 5.4.4 Conformance to IEEE 279'-1971 and IEEE 603-1980 5.4.4.1- Single-Failure Criteria This portion of the instrumentation-upgrade will perform all safety func-tions required for a design basis event-in the presence of: (1) any' single:de--

tectable failure within the safety sys-cems concurrent with all identifiable but.nondetectable failures; (2 ) ' all, -

failures 1 caused by the single failure;

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PAGE . PROJECT AS$10NMENT NO. M EU. NO.

58 o,81 90-013_ 0 Northeast Utilities Service Company

. NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION PROJECT TITLE DRAFT-1 CONNECTICUT YANKEE MODERNIZE-FEEDWATER CONTROL j PROJLCT e

and (3) all failures and spurious sys-tem actions which cause or are caused 1

by the design basis event requiring the Safety function.

l This plant; design change will enhance the adherence to the single failure

' criteria by:-

a) Increasing: channel and train inde-

! pendence and-redundancy.

b) Providing a deaign and test scheme to eliminate identified 4

nondetectable failures.

c) Reducing potential cascaded and de-sign' basis event failures, d) Eliminating certain common mode failures through the use'of quali-fied. Class lE components.

Specific safety implications are'iden-tified and addressed in the safety evaluations .-- ,

5.4.4.2 Completion ~of Protection; Action 4 The Reactor Trip-' Logic Cabinets are i designed so that, once initiated auto-matically.or' manually, the intended-sequence of protective actions of'the.

execute features willicontinue until completion.

5.4.4.3 Quality a

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ED3463-2 CEV 2-64 PAGE - PROJECT A$$iGNMENT No. RIV No.

59 o,81 90-013 0 Northeast Utilities Service Company NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION 1

PROJECT TITLE l DRAFT CONNECTICUT YANKEE I MODERNIZE FEEDWATER CONTROL PROJECT 1

^.

Components and modules used in this plant design change are of a quality

that is consistent with minimum maini-tenance requirements and low failure rates. The following-failure rate in-formation is-applicable to this' design:

j Rosemount Transmitters MTBF = l'9 years-MTBF = 5.84 SPEC 2001 Micro Card 2CCA-S

_yeart SPEC 200 Micro Card'2CCA-D MTBF = 4.84 years SPEC 200 Analog Modules MTBF = 30 years

-l Note: Since the SPEC 200 Micro Cards _'

, are relatively.new in compari-son to-other equipment, published MTBF; figures are low-er biased-since less historical' data is available.

5.4.4.4 Equipment Qualification-Safety system equipment used in this plant design change is Class 1E quali-fied in accordance with IEEE Std. 323-1974.

5.4.4.5= System ' Integrity

~

The-safety system equipment used in this plant design change is designed to accomplish its safety junction'under-the. full range'of applicable conditions enumerated in:the. design-basis.-

5.4.4.6 Independence , .

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EDH63-2 CEV #44 PAOL PROJECT AtsiONMENT NO. REv NO, 60 o,81 90-013 0-Northeast Utilities Service Company ;

NIPCLEAR ENGINEERING & OPERATIONS :

! PROJECT DESCRIPTION a

PROJECT TITLE DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER' CONTROL PROJECT Physical separation and electrical iso-lation is provided in this plant design change to maintain the independence of Class lE circuits and equipment.

Physical separation of redundant trains and channels of instrumentation is pro-vided as follows:

Containment protection-instrumenta-tion cabling is separated by chan-nel segregated conduit.

Protection instrumentation cabling through containment penetration are separated b:r distance between chan-nel segregated penetration groups.

Cable vault protection instrumenta-tion cabling isfseparated by chan-nel segregated conduit and cable q tray.

Protection Instrumentation cabling from the cable vault to the Control Room is through a common duct-bank i and cable tray,- This is remanent of the original plant-design in which separation. requirements were not applicable. Cabling to protec-tion instrumentation required'for safe shutdown duringsfire scenarios is, however, separated as a result of PA 83-117 modifications.

' Main Control Board cabling'and wir-ing is not train or channel sepa-rated. ,

~2 TBS 4P,07M

PAGE PROJECT AssiONMENT NO. Atv. No.

61 e,81 90-013 0 Northeast Utilities Service Company NUCLEAR ENGINEERING &'OPERATl0NS '

PROJECT DESCRIPTION PROJECT TITLE DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL M OJECT

Cabling from the Main Control Board to the existing Foxboro racks is

^

channel and train separated through the use of enclosed split wireway.

Channel 1 instrumentation cable is routed in one half of the Channel 1 wireway while Channel 1 power cabling and associated control-cabling is. routed in the other half. This arrangement represents Channel's 2, 3, and 4, as well.

Train A (Channel's 1 and.2) is physically separated-from Train B (Channel's 3 and 4).

3 e Cabling from the Main Control Board '

to the new Foxboro protection racks is channel and-train separated- ,

i through the use of separate conduit.

Cabling from the new and existing Foxboro protection racks to the-Reactor Protection. Logic Cabinets is train and channel segregated

'using conduit and enclosed split- '

wireways. . The Train A split .

wireway houses Channels 1 and-2, while the Train B split; wireway houses Channels 3 and-:4.

Non-Class lE annunciation and com-puter point cabling is housed in separate conduit =and enclosed split' wireway.

Physical separation of redundant-Foxboro protection racks is provid -

ed by distance and physical bar,ri-ers.

2 TBS 4P,07N e

PAGE PROJECT AttiONMENT NO mtv. No.

I 62 o,81 90-013 0 Northeast Utilities Service Company 1 NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION PROJECT TITLE 1

DRAFT .

4 .

CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL r PROJECT Electrical isolation between7 safety and .

nonsafety circuitry is provided by qualified Class lE analog and-digital isolation devices.. Isolation device application, in'_ control and instrumen--

' tation circuits, is in accordance with~

" IEEE Std._ 384-1981, Figure 1.

5.4.4.7 Capability for Test and Calibration Capability for testing and. calibration of safety systems. equipment.will be provided while retaining-the capability-i of the safety systems to accomplish their safety functions during power operation. This testing and calibra-tion will-duplicate, .as closely as practicable, performance of the safety -

function.

This modification' allows test signal injection of an appropriate magnitude to verify reactor trip setpoints-of each redundant portion of-the safety system and Reactor Trip. Logic verifica--

tion 1through the generation of " half" Reactor Trips. Verification of Reactor Trip coincidence logic is.also avail-able.

5.4.4.8 Information' Displays DisplayE infornation will be provided.

for manually controlled actions for

' which no automatic control.is provided.

Display information will provide accu-

-rate,= complete,.and timely information 4

pertinent to safety-system-status..

Indication of. bypass conditions wil'l.be

.2 TBS 4P,07M

.i .

203463-2 REY.244 - PROJECT ASSiONMENT NO, REV,NQ.

PAGE -

63 ,,81 90-013 0 Northeast Utilities Service Company NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION.

~PA0 JECT TITLE DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL PMDJECT provided in the Control Room. Informa-tion displays provided for manually Controlled protective actions will be visible from the location of the Con-trols uSed to effect-the actions.

5.4.5 Transmitters This plant design Change will replace /addlthe following Category 1, Class 1E transmitters: <

TRANSMITTER ESCRIPTION RANGE PT-1201-1B SG #1 PRESSURE CHANNEL B .O to 1200 PSIG PT-1201-2B SG #2 PRESSURE CHANNEL B 0 to 1200 PSIG PT-1201-3B SG #3 PRESSURE CHANNEL B 0 to 1200 PSIG PT-1231-4B SG #4 PRESSURE CMANNEL B .O to 1200 PSIG FT-120?-1 SG #1 STEAM LINE BREAK FLOW -27 to 270 in.: H O2 FT-1202-2 SG #2 STEAM LINE BREAK FLOW -27 to 270 in. H 2 O FT-1202-3 SG #3 STEAM LINE BREAK FLOW -27 to 270 in. H 2 O FT-1202-4 SG 04 STEAM LINE BREAK FLOW -27 to 270 in. Hao FT-1301-1B SG #1 FEED FLOW CHANNEL B - O to 528.74 in. H O 2 FT-1301-2B SG #2 FEED FLOW CHANNEL B. O to 531.22 in. - H 20-FT-1301-3B SG #3 FEED FLOW CHANNEL B .O to 533.56 in. H O 2 FT-1301-4B SG #4 FEED FLOW CHANNEL.B

< - 0 to 529.51 in. H 2 O FT-1301-1C SG #1 FEED FLOW CHANNEL C 0 to'528,74.in. H 2 O FT-1301-2C SG #2 FEED FLOW CHANNEL C 0 to 531.22in. Hao

FT-1301-3D SG #3 FEED FLOW CHANNEL D--- O to 533.56 in. H O 2 FT-1301-4D SG #4 FEED FLOW CHANNEL D 0 to 529.51 in. H O 2 FT-1201-1B- SG #1 STEAM FLOW CHANNEL B 0 to 573.65 in. H 2 O FT-1201-2B' SG #2 STEAM FLOW CHANNEL B 0 to 573.65 in. Hao FT-1201-3B SG #3 STEAM FLOW CHANNEL B -0 to 573.65 in. H 02 :

0 to 573.65 in. H O FT-1201-4B SG #4 STEAM FLOW-CHANNEL B. 2 FT-1201-1C SG #1 STEAM FLOW CHANNEL'C 0 to 573.65 in. H 2 O FT-1201-2C 'SG #2 STEAM FLOW CHANNEL C 0 to 573.65 in. Hao FT-1201-3D SG #3 STEAM FLOW CHANNEL D- 0- to 573.65 in. H 0 2

'FT-1201-4D SG #4 STEAM FLOW' CHANNEL D . O to 573. 65 in. - Hao LT-1301-1A SG #1 NARROW RANGE LEVEL CHANNEL A 82.3 to 17.6 in. H O - 2 LT-1301-2A SG #2 NARROW RANGE LEVEL CHANNEL A 82.3 to 17.6 in. H 0- 2 LT-1301-3A- .SG #3 NARROW RANGE LEVEL CHANNEL A 82.3 to 17.6 in'. H O 2 LT-1301-4A SG #4 NARROW RANGE LEVEL CHANNEL A 82.3 to 17.6 in. H O 2 2 TBS 4P.07N J

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

e EDMGM CEEI H DAGE pm0 JECT A9610NMENT NO, REv. NO.

64 o,81 90-013 0 Northeast Utilities Service Company.

NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION PROJECT TITLE DRAFT a

CONNECTICUT YANKEE

. MODERNIZE FEEDWATER CONTROL PROJECT.

LT-1301-1C SG #1 NARROW RANGE LEVEL CHA!ML C 82.3 to 17.6 in. Hao LT-1301-2C SG #2 NARROW RANGE LEVEL CHANNEL C 82.3 to 17.6 in. H O 2 LT-1301-3C SG #3 NARROW RANGE LEVEL CHANNEL C 82.3 to 17.6 in. H O 2 LT-1301-4C SG #4 NARROW RANGE LEVEL CHANNEL C 82.3 to 17.6 in. H O 2 LT-1301-1D SG #1 NARROW RANGE LEVEL CHANNEL D 82.3 to 17.6'in. Hao LT-1301-2D SG #2 NARROW RANGE LEVEL CHAtM L D 82.3 to 17.6 in. H O 2 LT-1301-3D SG #3 NARROW RANGE LEVEL CHANNEL D - 82.3 to 17.6 in. H O 2 LT-1301-4D SG #4 NARROW RANGE LWEL CHANNEL D 82.3 to 17.6 in. H O2 5.4.6 Indicators

}' This plant design Change will replace / add the j following Category 1, Class 1E-indicators INDICATOR DESCRIPTION RANGE 4 FI-1301-1B/FI-1301-1C SG #1 FEED FLOW CHANNEL B &-C- O to 2.5PPH X 10' FI-1301-2B/FI-1301-2C SG #2 FEED FLOW CHANNEL B & C 0 to 2.5PPH X 105 FI-1301-3B/FI-1301-3D SG #3 FRED FLOW CHANNEL B & D 0 to 2.5PPH X 10' FI-1301-4B/FI-1301-4D SG #4 FEED FLOW CHANNEL B & D' 0 to 2.5PPH X 10' FI-1201-1B/FI-1201-1C SG #1 STEAM FLOW CHANNEL B & C 0 to 2.5PPH X 10' FI-1201-2B/FI-1201-2C . SG #2 STEAM FLOW CHANNEL B & C 0 to 2.5PPH X 10' FI-1201-3B/FI-1201-3D SG #3 STEAM FLOW CHANNEL B & D 0 to 2.5PPH X 10' FI-1201-4B/FI-1201-4D SG #4 STEAM FLOW CHANNEL B & D 'O' to 2.5PPH X 10' LI-1301-1A SG #1 NARROW RANGE LEVEL CHANNEL A' O to 100%

LI-1301-2A SG #2 NARROW RANGE LEVEL CHANNEL A -O to 100%

, LI-1301-3A SG #3 NARROW RANGE LEVEL CHANNFL A 0 to 100%

LI-1301-4A SG #4 NARROW RANGE LEVEL CHANNEL ~A 0 to 100%

LI-1301-1C SG #1 NARROW' RANGE LEVEL CHANNEL C 0 to 100%

LI-1301-2C SG #2 NARROW RANGE LEVEL CHANNEL C 0 to 100%

LI-1301-3C SG #3 NARROW RANGE LEVEL CHANNEL C 0 to 100%

LI-1301-4C SG #4 NARROW RANGE LEVEL CHANNEL C 0 to 100%

LI-1301-1D SG #1 NARROW RANGE LEVEL CHANNEL D 0 to 100%

LI-1301-2D SG.#2 NARROW RANGE LEVEL CHANNEL D- O to 100%

LI-1301-3D SG #3 NARROW RANGE LEVEL CHANNEL D'- O to 100%

LI-1301-4D SG #4 NARROW RANGE LEVEL CHANNEL D 0 to 100%-

PI-1201-1B/PI-1201-1C SG #1 PRESSURE CHANNEL B &.C 0 to 1200 PSIG PI-1201-2B/PI-1201-2C SG #2 PRESSURE CHANNEL B & C 0 to 1200 PSIG PI-1201-3B/PI-1201-3D- SG #3 PRESSURE CHANNEL B & -D 0 to 1200 PSIG PI-1201-4B/PI-1201-4D ' SG #4 PRESSURE CHANNEL B & D. O to 1200:PSIG FI-1202-1 SG #1 STEAM LINE BREAK FLOW 0 to 150%

FI-1202-2 SG #2 STEAM LINE BREAK FLOW 0 to 150%

J 2 TBS 4P 07M

. _ _ _ _ _ _ _ _ _ . . ~ . _ _ _ . . _ . _ _ _ . _ . _ _ . . _ _ _ . _ _ . _ _

, , t tom >: cry a pmog5TTHITWENT No PAGE atv wo 65 e,81 90-013 0 Northeast Utlllties Service Company NUCLEAR ENolNEERING & OPEMATIONS PROJECT DESCRIPTION i

Phostcffifts -

DRAFT l COlitiECTICOT YANKEE MODERNIZE FEEDWATER CONTROL PhDstC1 o

FIa1202-3 SG #3 STEAM LIllE BREAK FLOW 0 to 150% !

FI-1202-4 SG #4 STEAM LiliE

REAR FLOWL 0 to 150% ,

LI-1302-1A/LI-1302 1B SG #1 WIDE RA!1GE LEVEL CilAlalEL D & C 0 to 3004 LI-1302-24/LI-1302-2D SO #2 WIDE RA!1GE LEVEL CHAlit1EL B & C 0 to 100%~

LI 1302*3A/LI-1302-3B SG #3 WIDE RA!JCE LEVEL CHAICIEL B 1: C 0 to 1004 L1-1302-4A/LI-1302 4B SG #4 WIDE RA!1GE LEVEL CllA11NEL D L'C 0 to 1004 F1-1301-1 So #1 AUXILIARY FEED FLOW 0.to 600-GiH FI-1301-2 SG #1 AUXILIARY FEED FLOW 0 t.o 600 GPH FI-1391-3 S0 #1 AUXILIARY FEED FLOW 0 to 600 GPM FI-1301-4 S0 #1 AUXILIARY FEED FLOW 0 to 600 GFH 5.4.7 Recorders-This-plant design change will replace / add the following non-safety-related-recorders: ,

RECORDER DESCRIPTIQlj BAllGE FR-1201-1/PR-1301-1 SG #1 STEAM / FEED Flow 0 to.2.5PPH X 10' FR-1201-2/FR-1301-2 So #2 STEAM / FEED FLOW 0 to 2.5PPH X 10' FR-1701-3/FR-1301-3 SG-#3 STEAM / FEED FLOW- O to 2.5PPH X 10' FR-1201-4/FR-1301-4 SG #4 STEAM / FEED FLOW 0 to 2.5PPH X 10';

LR-1301-1 SG W1 NARROW PallGE LEVEL 0 t0 100%-

LR-1301-2. SG #2 !1 ARROW RAli3E LEVEL 0 to 1004.

LR-1301-3 SG #3.11 ARROW RA!!GE LEV;CL 0 to 100%.

LR-1301-4 SG da NARROW RANGE LEV 3L 0.to 100%

These recorders may not.be utilized *to provide

~

Note:

future: Regulatory Guide.1.97 indication (T/pe A).

as they are not qualified.. Qualified units were proposed to meet potential-. future needs, howev-er, plantc operators preferred the design charac-

~' teristics of.the.above nonqualified-units.-

5.4.8 Ant.0/ Manual stations This plant designichange will replace / add the' l following non-safety-relate 6'A/M Stations:' .I

'l I

2 TBS 4P.0ht' ]

u q

-J

' e PAGE PmostCT A55tGNMENT NO- mEv ho.

[

66 o,81 90-013 0-Northeast Utilities Service Company NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION

Ecstet titos DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL PhostC1 37hTipfj DESCRIPT W FC-1301-1 SG #1 Main Feed Regulating Valve FC-1301-2 SG #2 Main Feed Regulating Valve FC-1301-3 SG #3 Main Feed Regulating Valve

-FC-1301-4 SG #4 Main Feed Regulating Valve HC-1201-1 SG #1 Auxiliary Feed Regulating Valve HC-1201-2 .SG #2 Auxiliary Feed Regulating Valve 11C-1201-3 SG #3 Auxiliary Feed Regulating Valve HC-1201-4 SG #4 Auxiliary Feed Regulating Valve 5.4.9 Annunciators Existing Main Control Board annunciators will be maintained, however,.certain rearrangement is necessary. Bistable inputs will be provided by

-the new equipment. In addition,--the following Main Control Board Annunciators will be added or changed 1 W111DOW DESCRIPTIOf1 E111U/E111b SG #1 STEAM FLOW / FEED FLOW DEVIAT1011 E112U/E112L SG #2 STEAM FLOW / FEED FLOW DEVIATION E113U/E113L SG #3 STEAM FLOW / FEED FLOW DEVIATION E114U/E114L SG #4 STEAM FLOW / FEED FLOW DEVIATION E121U/E121L SG #1 LEVEL DEVIATION /HIGH LEVEL-E1220/E122L SG #2 LEVEL DEVIATION /HIGH LEVEL- '

E123U/E123L SG #3 LEVEL DEVIATION /HIGH LEVEL E1240/E124L 'SG #4 LEVEL DEVIATION /HIGH LEVEL

-F218U/F218L SG #1 OVERFILL l'ROTECTION ACTUATED /LO-LO LEVEL F2190/F219L SG #2 OVERFILL PROTECTION ACTUATED /LO-LO LEVEL F2200/F220L SG #3 OVERFILL PROTECTION ACTUATED /LO-LO LEVEL F221U/F221L SG #4 OVERFILL PROTECTION ACTUATED /LO-LO LEVEL F237 FWCS CARD FAILURE-G128 A/B VITAL AC TROUBLE o

s 2 TBS 4P.07N

.: n .

1 I# PAot PmostcT ABOONWtNT No. At v. No 67 o,81 90-013 0 Northeast Utilities service Company !

NUCLEAR EN0lNEERING & OPERATIONS PROJECT DESCRIPTION }

1 PAcatCT TITLt t I

[ DRAFT i CON!1ECTICUT YANKEE *

- MODERNIZE FEEDWATER CONTROL 4

'nonct i

Y, Also, the following Main Control Board Annunciators f j will be deleted:

E117 STEAM LINE DREAK SIGt1AL LOW E119 SG LEVEL TRA11SMITTER SICt1AL HI '

F237 FEEDWATER 10 VDC FAILURE 0128 VITAL BUS 11NERTER OFF 5.4.10 Comouter Points

! Existing analog and digital Computer points will be maintained.-. Bistable and signal inputs will be provided by the new equipment. In addition, the following Computer points will be added:

i' Al1ALOG a

SG #1 11 ARROW RANGE LEVEL CHAN!EL A 0-100% 0-10.24V SG #1 NARROW RA!1GE LEVEL CHAlalEL C 0-100% 0-10.24V SG #1 11 ARROW RA11GE LEVEL CHAlaEL D 0-100% 0-10.24V I SG #2 NARROW RANGE LEVEL CHANNEL A 0-100% 0-10.24V.

' SG #2 11 ARROW RA11GE LEVEL CHAT #fEL C 0-1004: 0-10.24V

< SG #2 NARROW RANGE LEVEL CHAiniEL D 0-100% 0-10.24V SG #3 NARROW RANGE LEVEL CHA!DIEL A 100% 0-10.24V ,

SG #3 NARROW RANGE LEVEL CHAN!EL C 0-100% 0-10.24V i SG #3 NARROW RANGE LEVEL CHAIRIEL D 0-100%. 0-10.24V SG #4 11 ARROW RANGE LEVEL CHA!aEL A 0-100% 0-10.24V '

SG #4 NARROW RA11GE LEVEL CHA! RIEL C . 0-100% 0-10.24V SG #4 NARROW RA!1GE LEVEL CHAl#EL D 0-100% 0-10.24V SG #1 FEEDWATER FLOW CRA!TNEL C 0-2. 5PPH X 10' 0-80mV SG #2 PEEDWATER FLOW CHANNEL C 0-2.5PPH X 10'. 0-80mV SG #3 FEEDWATER FLOW CHAN!iEL D 0-2.5PPH X 10' 0-80mV SG #4 FEEDWATER FLOW CHAIREL D 0-2.5PPH X 10' 0-80mV SG #1 STEAM FLOW CHAlcEL B 0-2.5PPH X 10' 0-80mV-SG #2 STEAM FLOW CllANNEL B' 0-2.5PPH X 10' 0-80mV SG #3 STEAM FLOW CHANNEL B 0-2.5PPH X 10' 0-80mV SG #4 STEAM FLOW CHANNEL B 0-2.5PPH X 10 8 0-80mV SG #1 STEAM FLOW CHA!1NEL C 0-2.5PPH X 10' 0-80mV e SG #2 STEAM FLOW CHANNEL C 0-2.5PPH X 10' 0-80mV 2TB54F.07N

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

.J PAOL PmostCT AlliONutNT NO 68 o,81 90-013 abv. NO Northeast Utllities Service Company a

NUCLEAR ENGINEERING & OPERATIONS j PROJECT DESCRIPTION l l

" i PhostCT TITLE

DRAFT CONNECTICUT YANKEE I MODERNIZE FEEDWATER CONTROL

, W$ teT

! SG #3 STEAM FLOW CHA!DIEL D 0-2.5Pril X 10' 0-80mv 50 #4 STEAM FLOW CHA!niEL D 0-2.5FPH X 10' 0-80mV-i 0-1200 PSIG 0-1.24V SG #1 PRESSURE CHA!niEL B SG #2 PRESSURE CHAlafEL B 0-1200 PSIG 0-1.24V SG #3 PRESSURE ClWHEL B 0-1200 PSIG 0-1.24V SG #4 PRESSURE CHAtamL B 0-1200 PSIG 0-1.24V Dio1TAL SG #1 !!R LEVEL CHAN!!EL A HIGH/ NORMAL SG #1 NR LEVEL CHA!UTEL C HIGH/110RMAL l SG #1 NR LEVEL CHA!UTEL D HIGH/ NORMAL t

! SG #2 NR LEVEL CHA!DIEL A HIGH/ NORMAL i SG #2 NR LEVEL CHAlfNEL C HIGH/110RMAL SG #2 HR LEVEL CHANNEL D HIGil/ NORMAL l

3 SG #3 NR LEVEL CHA! RIEL A llIGH/ NORMAL SG #3 NR LEVEL CHA! RIEL C HIGH/ NORMAL SG #3 NR LEVEL CHA!!!iEL D HIGH/ NORMAL SG #4 NR LEVEL CHA!1NEL A HIGH/ NORMAL SG #4 NR LEVEL CHA11NEL C HIGH/ NORMAL SG #4 NR LEVEL CHAtRIEL D llIGH/ NORMAL t

1 SG #1 liR LEVEL DEVIATION HIGH/ NORMAL SG #2 NR LEVEL DEVIATION HIGH/ NORMAL SG #3 !"4 LEVEL DEVIATION HIGH/ NORMAL-SG #411R LEVEL DEVIATION HIGH/ NORMAL i

SG #1 STEAM FLOW DEVIATION HIGH/ NORMAL

~

SG #2 STEAM FLOW DEVIATION HIGH/ NORMAL-SG #3 STEAM FLOW DEVIATION HIGH/ NORMAL SG #4 STEAM FLOW DEVIATION HIGH/ NORMAL SG #1 FEED FLOW DEVIATION HIGH/ NORMAL-SG #2 FEED FLOW DEVIATION HIGH/ NORMAL SG #3 FEED FLOW DEVIATION HIGH/ NORMAL' SG #4 FEED FLOW DEVIATION HIGH/ NORMAL SG #1 XFER SWITCH STATUS ABNORM / NORMAL SG #2 XFER SWITCH STATUS ABNORM / NORMAL SG #3 XFER SWITCH STATUS ABNORM / NORMAL SG #4 XFER SWITCH STATUS ABNORM / NORMAL r.

SG #1 FWCS CARD FAILURE 2 TBS 4r 07N l

O 1

i ;

topnf alv #44 '

PAQt PhostCT All:0NWINT NO. StV ho ;

I 69 o,81 90-013 0

{

Northeast Utilities Service Company _!

! NUCLEAR ENolNEERING & OPERATIONS !

I '

PROJECT DESCRIPTION 1

i i emostet titte

. DEAEI :

CO!iNECTICUT YANKEE :

MODER1417,E FEEDWATER CONTROL [

]

j- enostet

- ~~

I.

l I

SG #2 FWCC CARD FAILURE SG #3 FWCS-CARD FAILURE

{ SG #4 FWCS CARD FAltVRE 1

l SG #1 OVERFILL PROTECTIOll-ACTUATED / NORMAL i SG #2 OVERFILL PROTECTIO!1 ACTUATED /130l04AL SG #3 OVERFILL PROTECTIO 11 ACTUATED / NORMAL j' SG #4 OVERFILL PROTECTIO!1 ACTUATED /t10RMAL i

5.4.11 SPEC 200 Micro Usaae i

i The_ acceptability of-Foxboro SPEC 200 Micro j equipment usage.in safety systems of Nuclear -

4 Power Generating Stations including software 3

validation.and verification is documented in Foxboro Test' Reports QOAAE01,-QOAAE03,.QOAAE04, . !

and QOAAE05.- ;

i . .

l In addition, interference i formed and is documented _i. testing has n-Foxboro been Test per-Report'

No. 88-1033a. This testing includes EMI and RFI

!~

testing. NUSCO will also contract an indepen- !

dent consultant'to perform an' evaluation i

including testing to determine that the equip- '

ment will be electromagnetically compatible with the environment.

e 5.4'.12 Ecuinment Power Sources ;

. Power'to the Foxboro rack. equipment will be ,

--provided'as-follows:

Analog:-Rack _'lF- Vital Ai ;

Analog Rack 2F . Vital Bj j

-Analog. Rack 3F- Vita 1 C ;

Analog Rack 4F- Vital D' Protection. Rack 1R Vital-A- I 4-

' Protection Rack 2R- Vital B

s

.2TB34P.07M

>]

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

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

i l

1

""'""'* paos pnosect Ass 4 wast so nov wo 70 e,81 90-013 0 Northeast Utilities Service Company

. NUCLEAR ENolNEERING & OPERATIONS j PROJECT DESCRIPTION 1

i PnostCt title i DRAFT '

-i l i CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL ,

Tiiostet i :

~

Protection Rack 3R V i t a l-- C . -"

! Protection Rack 4R Vital D Semi-Vital I Control Rack Fl/2 control Rack F3/4 Semi-Vital-5.5 Imniementation Plan-j 5.5.1 general ~

a) .This plant _ design. change will be installed

-and tested prior to completion of'the 1993 refueling outage. Precautions shall'be taken during implementation.to_ ensure _that minimum channel operability requirements are adhered'to, b) _The majority of the work' associated with

this change will_be performed during the~

outage,-however, pre-outage work will be >

necessary _ to assure con.pletion within the planned duration of the outage. Pre-outage work will be controlled by PDCR'Section 4, a Early Approval for Construction and-the AWO l . program. ,

c) All electrical work ~shall' be performed in' accordance with NUSCO Specification

, SP-EE-076, Standard Specification for-Elec . '

trical Installations as a. guide. 'All in-strumentation andiinstrument-tubing shall-be installed'per NUSCO_ Specification SP-EE-275; Specification for Instrumentation Installa- '

tion, Piping, . andL . Tubing.

l ld) Any cables, portions of cables or wires left l -abandoned'in' place shall.be__in ac'cordance-with CY ~ procedure ACP 1.0-3.5, " Permanently

Lifted Leads."

2 TBS (P.07N

- ,~ -,. . , , - , - . ,, ,-, , , .,,,-: .,,

t i

b PAQ$ PAQs(CT A$$r3NW(NT NO

71 ,,81 90-013 R$V NO 1

Northeast Utilities Service Company l 4 NUCLEAR ENolNEERING & OPERATIONS

! PROJECT DESCRIPTION t 4

i ~r hostet 14 tit l DRAFT l CONNECTICUT. YANKEE l j MODERNIZE FEEDWATER CONTRCL

] Ptostct - - -

i d.

l 5.5.2 Pre-outaae construction -

~

i a) NUSCO GENERATION CONSTRUCTION (or designee) will prefabricate two transmitter racks and ;

} eight seismic transmitter mounts.

4 i b) NUSCO GENERATION CONSTRUCTION (or' designee) will install two transmitter racks in the '

Turbine Building. Instrument tubing, j valving, conduit, and cabling will;be in- .

i stalled to facilitate = timely connection i during the outage.

I c) NUSCO GENERATION CONSTRUCTION (or designee) will seismically install two 2-bay second- ,

ary-side Reactor Protection cabinets (with :

caps and skirts) behind the Main Control ,

e Board.

d) NUSCO GENERATION CONSTRUCTION (or designee)-

will seismically install conduit from each

secondary-side Reactor Protection cabinet to

!. the-Main Control Board,-the Reactor Trip

! Logic Cabinets, and to the other secondary-side Reactor Protection cabinet.-

e) NUSCO. GENERATION TEST'(or designee).'will pull instrument cable in the new conduit; ,

runs. Wires will- be terminated--'in the new t

cabinets and left coiled at the other: end for connections during_the outage.

1 f) NUSCO GENERATION TEST (or designee) will prefabricate Main Control Board mounting plates to.. facilitate board equipment instal-lation during the outage.

5.5.3 Ontaae construction o-2 TBS 4h 07N

~I

.h'

-. ., ~ . . - . - . . . . --.- - , , .- +-. . - . , ., > ,

1 Past PAostCT AlliGNMENT NO AtY No.

72 ,,81 013 0

Northeast Utilities Service Company

} NUCLEAR ENolNEERING & OPERATIONS j PROJECT DESCRIPTION-i d

~PhostC1 fif &L DRAFT l CONNECTICUT YANKEE 1 MODERNIZE FEEDWATER CONTROL rnodet J

a) NUSCO' GENERATION TEST (or designee) will determinate existing' wiring'to the Hagan'~

> Feedwater Control System and will protect j_

the wiring from damage.

, b) CYAPCO I&C will remove the old Hagan.cabi-nets and INSCO GENERATION CONSTRUCTION (or designee) will seismically (2-over-1) in-

] stall the new Foxboro cabinets in their-

place.

1

! c) NUSCO GENERATION TEST (or designee) will pull and terminate all new/ existing cables to/from the Main Control Board to/from the

Foxboro cabinets, d) NUSCO GENERATION-CONSTRUCTION (or designee) will install-.eight seismic transmitter mounts in the mid-level Containment-Outer Anulus, e)- NUSCO GENERATION CONSTRUCTION.(or designee) will~ install all' associated instrument tub- ,

ing, valving,' conduit, and cable to the new. i transmitter locations.

f) NUSCO GENERATION CONSTRUCTION and/or CYAPCO I&C (or their designees).will mount all-transmitters,. connect all' instrument tubing, and terminate all transmitter wiring,.

g) NUSCO GENERATION TESTL(or. designee)-wil1~

terminate wiring on-both sides of the. con-tainment penetration assemblies.

h) 'NUSCO GENERATION. TEST'(or designee) will mountfnew Main Control-Board equipment in place'of.the obsolete. equipment.-. ,.

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'D*""* PAst emostet AssiowtNT No nav wo j 73 o,81 90-013 0 l

} .

Northeast Utilities Service Company I

NUCLEAR ENQlNEERING & OPERATIONS -

l PROJECT DESCRIPfl0N ,

i thostCi tatLL DRAFT !

CONNECTICUT YANKEE :

MODERNIZE FEEDWATER CONTROL ;

j +ngstet i

j i) NUSCO GENERATION TEST-(or designee) will . I i -perform Main Control Board-wiring changes and equipment removals / additions.

} !

i j) CYAPCO I&C7(or designee) will rearrange 1the 3

existing Reactor Trip' Logic cabinets 1to l provide annunciation and computer points'for secondary-side inputs.

! k) CYAPCO I&C (or_. designee).will install I/P l

. converters and interface the new equipment ,

j with the old final control elements.

1

! 1)- NUSCO GENERATION TEST (or designee) will i determinate existing wiring to the Vital A 4 and B. inverters and will; protect-the wiring i from damage- .

_ 4 NUSCO GENERATION CONSTRUCTION'(or-designee) m) ,

willJremove the old Vital A and B inverters,. .

< the_ abandoned Vital C:and D inverters.and

! the ventilation hood'and seismically install' two Class 1E 5.kVA inverters and back-up transformers.in Switchgear Room A..

t

n) _ NUSCO GENERATION CONSTRUCTION (or' designee)- l

< will seismically-' install' conduit from each

' ' inverter to the control room floor _penetra- "

tion and to_ existing cable tray.

o): NUSCO_' GENERATION TEST (orLdesignee) will

-pull and terminate all new/ existing cables to/from the-inverters.

5. 6 Test ' Plan -

~

l 516.11 Construction Phase'Testina:

5.6.l'.1 As-Built 1 Verification: " l t

.. . . . ,-a._- . , , . - _ _ . d .. . - , . _ _ _ . . -_.-._m..._. . -_, - . ,,_

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Past enoseet Assiowest No niv wo.

74 o,81 90-013 0 Northeast Utllities Service Company NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION enostet tit 6 Illl&ET CONNECTICUT YANKEE ,

MODERNIZE FEEDWATER CONTROL PQostet

-a)- NUSCO GENERATION CONSTRUCTION and NUSCO GENERATION TEST (or their designees) will verify the correct arrangement and mounting of added Control Room and Switchgear Room A

-equipment (cabinets,-wireways,-con--

duit, and Control Board mounted

- equipment). Signed as-built draw-ings shall be delivered to the Plant Engineer depicting the actual arrangements-and all as-built -

changes.

b) CYAPCO I&C will verify the'continu-ity and arrangement of_all rearranged wiring' internal to the-existing Foxboro Reactor Protection System (RPS)' Racks, as well as,-all-wiring-internal--to the new:Foxboro.-

Cabinets. This verification will be documented using a To/From wir -

ing list addressingLeach internal wire. Additionally, CYAPCO?I&C will verify the continuity and.ar-rangement_of_.all--wiring associated with transmitter replacements and additions. CYAPCO I&C will deliver signed as-built drawings to the Plant Engineer depicting the actual arrangements and all-.as-built _

changes, c) NUSCO GENERATION TEST will verify-the continuity and arrangement of all-wiring. external'to the Foxboro' RPS-Racks -(excluding transmitter

-wiring) and the new Foxboro Cabi -

nets. -NUSCO GENERATION TEST will deliver signed as-built-drawing's-to -

2 tbs 4P.07M

- _ _ . - . _ _ - _ _ _ _ - _ _ . - - - _ _ ~ - - --

l j !

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paot enostcT assiswa%t ho may so. l 1

75 o,81 90-013 0 -

j Northeast Utilities Service Company ,

NUCLEAR ENGINEERING & OPERATIONS i i PROJECT DESCRIPTION :

1 !

o j -emosset fint I

DRAFT

! CONNECTICUT YANKEE

- HODERNIZE FEEDWATER CONTROL emostet

). -

the plant-engineer depicting the .:

actual arrangements and~all i as-built changes.- Additionally, I

NUSCO-GENERATION TEST will perform i insulation resistance tests per PMP-i 9.8-7 on-all added power cables.-

d) NUSCO GENERATION CONSTRUCTION will verify the arrangement.of all field

mounted equipment (transmitter-i racks, transmitter mounts, instru-ment tubing, and instrument-conduit). -NUSCO GENERATION '

CONSTRUCTION will deliver signed' as-built drawings to the Plant En-l gineer depicting' actual equipment i arrangements and dimensions, as j well as, all as-built changes.

8-

Note: Signed as-built drawings will be i turned over to the Plant Engineer prior to preoperational testing _of the plant equipment.

5.6.1.2 Installation Documents Verification ,

a) All, installation AWOs will be-complete and signed off by Generation Test, Gen-eration Construction-andLInstrumenta-

- tion and. Controls._ All associated QC !

checks must be' complete and satistacto--

ry . -

b) The Project Engineerfand Plant Engineer will verify that the entire-scope of the~ project is complete _and-ready.for

~

turnover and testing.

?

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paos paostet AssioNwsN1 No sti No j 76 ,,81 90-013 0 -;

I Northeast Utilities Service Company NUCLEAR ENGINEERING & OPERATIONS .i

PROJECT DESCRIPTION !

l I

enostet titta

]

DRAFT ,

l CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL TiGret s t

, c) All Construction. Phase NCRs will be ;

dispositioned by the Project-Engineer !

and signed off through the Unit Super-intendent prior to testing. ,

Noter The above three items' apply to complete 2 and~ partial releases.- !

5.6.1.3 Pre-Installation Testing i

. a) Individual RPS component testing and inspection will.be' performed at the- -

Factory Acceptance Test per NUSCO Spec-

] ification SP-EE-323.

b) The proper operation of--transmitters,. ;

i recorders and indicators will be veri-fied by bench calibrations performed by=

CYAPCO I&C. .,

5.6.1.4 Installation Testing / Inspection. !

I a) GENERATION TEST and CYAPCO_I&C.will

] perform " Red-Line" Testing per CY ACP 1. 2-3. 8, ". Electrical .. Wiring Verifi-cation-Functional' Testing and Scheme Verification,' on their respective.por-tions of the modification. . The - -Proj ec t Engineer-and the Plant Engineer will-verify-that adequate._ overlap occurs

.between GT and'I&C prior to. -

energization of:the RPS equipment,

, 'b) Concrete anchor bolt and unistrut-clip installation will be performed lper Gen-

eration-~ Construction: approved procedures. '

5.6.2 Proonerational Testina I

2ttiser.01M 4

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e PAOL PAQJtCT AlliOWENT NQ Mtv NO 77o,81l 90-013 0 Northeast Utilltles Service Company NUCLEAR EN0lNEERING & OPERATIONS PROJECT DESCRIPTION WQstC1 TITLE DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL NOJtCT S.6.2.1 Power-Supply Testing CYAPCO I&C will_ test and adjust, as required, each-rack power supply to verify manufacturer's specifications.

Individual nest power supplies will then be tested and adjusted, as- i required,-to verify manufacturer's j specifications.

PHP 9.2-120 Foxboro SPEC 200 Multi-nest Power Supply Testing.

5.6.2.2 Loop Calibration and Loop Functional

- Testing- '

- CYAPCO I&C Surveillance. Procedures, Preventive Mainte' nance Procedures and -

- Special--Maintenance Procedures will be:

revised and performed,as preoperational tests to verify the correct calibration and functional operability of all devices affected by this' plant-design

- change? -The calibration verification test will prove that, with a known pre'-

cision input, the instrument or channel '

- gives the required output.. The func ;

tional verification test will prove that-the-tested equipment-is; capable;of performing its' design-functions includ-ing' proper' trip and alarm settings;-

proper operation of permissive,-prohib--

. it, and bypassifunctions; and operabil--

ity of trip and bypass switches..-The following procedures will be. revised,

. as necessary, and performed:

SUR 5.2-4.5 Rack 1F/1R' Periodic Surveillanc,e-(Monthly) 2 TBS 4P 07M

e j PAGE PhostCT Atti3NMENT NO htv No. l 78 o,81 90-013 0 j i Northeast Utilities Service Company i

NUCLEAR ENGINEERING & OPERATIONS

! PROJECT DESCRIPTION l

Ph04 TOT TITLE l DRAFT CONNECTICUT YANKEE j MODERNIZE FEEDWATER CONTROL l emostet i

l SUR 5.2-4.6 Rack 2F/2R Periodic Surveillance l (Monthly) 1 1 SUR 5.2-4.7 Rack 3F/3R Periodic. Surveillance I i _

(Monthly) ,._

SUR 5.2-4.8 Rack 4F/4R Periodic Surveillance

-(Monthly).

SUR 5.2.6.1 Steam Generator #1 Narrow Range,

' Level Calibration (Refueling) ,

SUR 5.2.6.2 Steam Generator #2 Narrow Range Level Calibration-(Refueling)_

SUR 5.2.6.3 Steam Generator #3 Narrow Range.

- Level Calibration (Refueling)

SUR 5.2.6.4 Steam Generator #_4-Narrow Range Level Calibration (Refueling)

, SUR 5.2-11.1A- Steam Generator #1 Train A Steam i Flow,-Feedwater Flow and Steam Generator' Pressure Channel Calibra-3 tion (Refueling)

SUR 5.2-11.2A Steam Generator #2 Train!A-Steam---

-Flows Feedwater Flow and Steam Generator. Pressure Channel.Calibra-tion-(Refueling)

SUR 5.2-11.3A Steam Generator #3 Train'A Steam Flow, Feedwater Flow and Steam-Generator Pressure Channel-Calibra-

+

tion (Refueling) i SUR 5.2-11.4A Steam Generator-#4 Train-A Steam Flow,'Feedwater Flow'and Steam Generator _ Pressure Channel:Calibra -

tion (Refueling)

SUR 5.2-11.1B Steam Generator'#1' Train B Steam

Flow;-Feedwater Flow and Steam-

' Generator Pressure Channel Calibra-4 tion :-(Refueling)

SUR 5.2-11.2B. . Steam Generator.-#2 B Steam Flow,

Feedwater Flow and--Steam Generator Pressure Channel Calibration (Refu-

!eling) -

-2 tbs 4P;0?H-

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

e touu a arv H e4ot paostet assiowtNT No alv No 79 e,81 90-013 0 Northeast Utilities Service Company NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPTION PAQstCT fifLt DRAFT CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL

>QOstC1 SUR 5.2-11.3B Steam Generator #3 B Steam Flow, Feedwater Flow and Steam Generator Prossure Channel Calibration (Refu-eling)

SUR 5.2-11.4B Steam Generator #4 B Steam Flow, Feedwater Flow and Steam Generator Pressure Channel. Calibration (Refu-eling)

SUR 5.2-38 Steam Line Break Channels 1-4 Cali -

bration (Refueling)--

SUR 5.2-50 Reactor Trip Checkout SUR 5.2-124.1 Reactor Trip Logic Cabinet Al Coincidence Test (Six Week)

SUR 5.2-124.2 Reactor Trip Logic Cabinet A2.

Coincidence Test (Six Week)

SUR 5.2-124.3 . Reactor = Trip Logic' Cabinet 1B1-Coincidence Test (Six Week) ;

SUR 5.2-124.4 Reactor Trip Logic Cabinet' B2 '

Coincidence Test (Six-Week)

PMP 9.2-120 Foxboro.Multinest. Power Supply Testing-PMP 9.2-161 Primary Side First Cut Annunciator Verification PMP 9.2-NEW.1 Loop 1'Feedwater. Control Calibra-tion PMP 9.2-NEW.2- Loop 2 Feedwater Control Calibra-tion FMP 9.2-NEW.3 Loop.3.Feedwater. Control Calibra-tion PMP 9.2-NEW.4' Loop 4 Feedwater Control Calibra-tion ST 11.2-X1 RPS Upgrade Phase..III (PDCR 1331-Safety Related Equipment) Pre-Oper-

. . ational Test.

ST 11.2-X2 RPS-Upgrade Phase III (PDCR 1331 Feedwater Control Equipment) Pre-Operational Test ST 11.2-X3- RPS P.hase III Integrated Test ,

2 TBS 4P.07M

i PAQs PhQ,itCT A$$#0WINT NQ hty NQ

, 80 o,81 90-013 0 i Northeast Utllities Service Company NUCLEAR ENolNEERING & OPERATIONS PROJECT DESCRIPTION j Y

] ekostettitLE d

DRAFT I CONNECTICUT YANKEE j MODERNIZE FEEDWATER CONTROL emostet i" ST ll.2-X4 Feedwater Control System Failure i Mode Verification-l CMP 8.2-26 Insertion and Restoration of Sig-~ :

i nals )

1 .

1 S.6.2.'3 Inverter Testing ]

I a) ' GENERATION TEST will perform Inverter ~ - '

i Phase I and Phase II tests.

4 b) GENERATION TEST will test molded case i circuit breakers in accordance with CY-procedure PMP 9.8-88, " Testing of Mold-1 ed Case Circuit Breakers and Motor Cir- '

cuit Protectors.'

5.6.2.4 Loss of Power Testing

This testing will'be performed to demonstrate redundancy and electrical-~inde-pendence. This testing <will also verify _

that all equipment affected by the loss of i

- power will fail.to a safe state.- The fol-lowing-test procedure will.be. Written'and performed:

i i

PMP-9.2-NEW.1 Loss of. Nest Power Panel 1R :

PMP 9.2-NEW.2- Loss of? Nest: Power Panel 2R PMP 9.2-NEW.3 Loss of Nest Power' Panel 3R PMP-9.2-NEW.4 Loss of Nest Power Panel 4R ,

.-5.6.2.5 Pressure Testing ,

CYAPCO OPERATIONS will-perform a visual -

check of all added or modified instrument :

-tubing.

5.6.3 Periodic Post-Installation Testina

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e 1 tD9n2 Rtv 244 PAGE PRostCT AlliON9 TNT NO aty NO 31 epi 90-013 0 Northeast Utilities Service Company NUCLEAR ENGINEERING & OPERATIONS PROJECT DESCRIPYlON i

ta0;tet tit 66 DEAE.T -

CONNECTICUT YANKEE MODERNIZE FEEDWATER CONTROL PROstC1 a) CYAPCO I&C. Surveillance Procedures will be performed periodically, as required by Tech-nical Specifications to verify operability of the safety system.

i 5.7 Ouality Ouestions i

l Does this plant design change involve systems, compo-j nents or structures that are i

i M lh2 3

QA Category 1 [x] [ ]

Radwaste QA [ }- [x]

Fire Protection QA [x] [ ]

ATWS QA [ ): (x)

S

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ML20128E681

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