ML20154Q373

ATWS Conceptual Design

ML20154Q373
Person / Time
Site:	Crystal River
Issue date:	11/12/1986
From:	Low R FLORIDA POWER CORP.
To:
Shared Package
ML20154Q359	List: 3F0988-17, Forwards Review Summary Re Relationship Between Ser,B&W Owners Group Generic ATWS Design & Util Conceptual Design,As Requested in NRC .Rept MAR 84-06-07-01, ATWS Conceptual Design Also Encl ML20154Q373
References
MAR-84-06-07-01, MAR-84-6-7-1, NUDOCS 8810030382
Download: ML20154Q373 (92)

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s MAR 84-06-07-01 AtlTICIPATED TRAtiSIENT WItHOUT SCRAM (ATUS)

C0ftCEPTUAL DESIGti R.H. Low

. FLORIDA POWER CORPORAT!0li NUGEM ENGW!!?.!MG CE?MTM!Nf l ) CRYSTAL Rr/ER Off!T 3 REVIEWED AND ACC'J* TED T/s

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i .f 84-06-07-01 FLORIDA POWER CORPORATION REI/ MAR NO.

Anticipated Transient

' Without Scram (ATWS)

Project Title t

Conceptual Design for Crystal River Unit 3 Nuclear Engineering f

r hY /0/del84 Prepared by 'Date

$A bhnb1) /W29/P6 Reviewed by bade

ANTICIPATED TRANSIENT WITHOUT SCRAM QTSTS) CONCEPTUAL DESIGN I. Proiect Desien Basis A. Snecific Codes and Standards The following applies for equipment being installed in existing safety systems to be environmentally qualified for normal operation and seismically qualified so as not to degrade the safety related equipmen'c.

The appl 1~sble codes and standards for interfaces between non-safety and safety systems are:

IEEE 279-1971 Criteria for Protection Systems for Section 4.7 Nuclear Power Generating Stations.

IEEE 323-1974 IEEE Standard for Qualifying Class lE Equipment for Nuclear Power Generating Stations.

IEEE 344-1975 Recommended Practices for Seismic Qualification of Class lE Equipment for Nuclear Power Generating Stations.

CR-3-E247-A Electrical Separation Criteria for control Boards, Equipment Cabinets and Relay Racks.

10CFR50 Appendix R The applicable NRC requirements concerning the ATWS System (Diverse Scram System (DSS) and ATWS Mitigating System Actuation Circuitry (AMSAC)) are:

10CFR50.62 Requirements for Reduction of Risk from Anticipated Transients Without Scram (ATWS) Events for Light-Water Cooled Nuclear Power Plants.

NRC Generic Quality Assurance Guidance for ATWS Letter 85-06 Equipment that is not safety-related.

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B. Safety Classification The ATWS system, DSS and AMSAC, are non-safety systems and these portions are described in the NRC Generic I,etter 85-06.  ?.1WS is not designed to meet IEEE 279, however it is designed and engineered for high reliability to preclude unnecessary challenges to existing safety systems. The interfaces with the safety related systems, Remote Shutdown System (RSS),

Gamma Metrics (GM), and Emergency Feedwater Initiation and Control System (EFIC) will be treated as safety related.

C. Identification of Maior Ecuinment r

1. Remote Shutdown Auxiliary Equipment (RSAE)

Cabinets: Provide DSS isolated analog signals for Reactor Coolant (RC) wide range pressure to the NNI cabinets.

2. Gamma Metrics channels: Provide AMSAC isolated analog signals for reactor power level to the NNI cabinets.

3. NNI Cabinets: a) Provide DSS test capability, signal processing of RC wide range pressure, and CRD trip and enable contact outputs, and b)

Provide AMSAC test capability, signal processing of MFW flow and reactor power level, alarm outputs, trip contact outputs to turbine generator main control board (MCB) TGR panel and Emergency Feedwater (EFW) initiate contact outputs to EFIC cabinets (A and D only).

4. CRDCS Cabinets: Provide DSS test capability, relay logic for trip enable, channel interlock, trip lockup / reset, alarm outputs, and SCR gate drive trip outputs to regulating rod group power supplies.

5. MCB TGR: Provide relay logic for AMSAC turbine generator trips.

6. EFIC Cabinets: Provide digital isolation for AMSAC trip inputs from NNI and the logic necessary to initiate EFW from anticipatory trip input.

7. SER Cabinet: Provide logic for test and trip alarms for DSS and AMSAC. This is a programming function only and will not require any internal rewiring.

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D. Functional Descrintion

1. DSS The principal function of the DSS is to prevent an ATWS by tripping the reactor if, for any reason, the rods have failed to drop in response to an RPS trip. The DSS must function to provide reactor trip, diverse from the existing Reactor Trip System (RTS), for all ATWS transients which require reactor trip (in addition to AMSAC actions) to prevent a potential for damaging over pressurization of the RCS. A design standard for DSS pressure limitation has been arbitrarily set at 3250 psia as stated in B&W Document 47-1158904-00.

2. AMSAC The principal function of the AMSAC is to mitigate the effects of an ATWS in the unlikely event of no rod drop from either RPS or DSS. The AMSAC must function to actuate EFW and trip the turbine on ATWS transient.a where required to prevent sorious RCS over pressurization, maintain fuel integrity and meet 10CFR release requirements. A design standard for AMSAC pressure limitation has been arbitrarily set at 4000 psia in accordance with the analyses in BAW-1610.

The ATWS transients of concern for the B&WOG plants have been shown to be the Loss of Main Feedwater (LMFW) and the Loss Of offsite Power (LOOP) leading to LMFW.

Consideration for avoidance of inadvertent actuation dictate that there be at least two channels, powered from separate sources, coupled with appropriate coincidence capability.

E. Preliminary Layouts See attachments 1 and 2.

F. Preliminary Flow Diacrans Not applicable 3

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<' G. Identification of Interfaces and Interface Recuiremgnt3 1

The interfaces with IE systems will be designed to meet l the applicable codes and standards listed in Section A above.  :

The following is a list of the interfaces:

1. DSS

, Fr.om I2 Isolation RSAE Cabinets A&B Non-Nuclear Instrumentation IE to IE (NNI) cabinets NNI Cabinets control Rod Drive Control 1E to 1E System (CRDCS) Cabinets CRDCS Cabinets Sequence of Events 1E to lE Recorder (SER)

2. AMSAC Gamma. Metrics (GM) Channels A&B NNI Cebinets lE to IE NNI Cabinets dFIC A&D IE to lE NNI Cabinets MCB TGR 1E to lE NNI Cabinets SER IE to IE See Preliminary Interface Requirenants, Attachment 3, for detailed interfaces.

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P H. Identification of control and Locic Recuirements, and All Interlocks

1. DSS & AMSAC

a. Primary input signals will be diverse from existing protection systems from the sensor output to final actuation device.

b. The system will be electrically independent from existing protection systems.

, c. Channel separation shall be provided in 4 accordance with plant specific requirements for routing non-safety signals.

d. The system shall be designed to minimize challenges to safety systems. This require-ment dictates the use of at least two channels with appropriate coincidence logic.

Both systems will employ an "energize-to-trip" logic.

a. To avoid the potential for inadvertent

, actuations of this non-safety system, the syctem shall be designed so as not to revert to a 1-out-of-1 status during channel test.

This dictates that the system shall become inoperable during channel test.

f. The system shall be designed such that electronic delay shall contribute no more than one second to the overall time required to actuate the final actuated device.

g. The system shall incorporate a channel test capability. All power tests shall be performed at 6 month intervals. Complete system tests shall be performed every refueling. The test function should simul-taneously test a channel together from sensor to final actuated device.

Except for DSS: Input sensors.

Except for AMSAC: Input sensors, final actuated device.

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h. The system shall be designed to provide status output to the control room for channel trip, system trip and test status.

2. DSS Only

a. The DSS shall cause a reactor trip by interrupting power to the SCR gate drivers for rod groups 5-7 and auxiliary power supplies by a means other than the existing

, SCR control relays driven by RPS.

b. To prevent CRDM damage due to rachet trip (attempted re-energization of CRDM with a i moving leadscrew) , the DSS shall incorporate trip lock up and manual reset activated by a true DSS trip.

c. DSS is based on using a Very High RCS Pressure input and shall use a setpoint of 2450 t 25 psig,

d. No startup bypass is required on DSS with the reactor coolant pressure signal as . the trip signal.

a. DSS channels shall be configured with a total input instrument s"ring error of no more than 1% under normal op6 ration.

l 3. AMSAC Dnly

a. The AMSAC shall initiate EFW and cause a r turbine trip by actuating devices that are within the existing circuitry for EFW initiation (EFIC) and the turbine trip circuits.

b. AMSAC shall be designed to actuate the AMSAC features on a trip setpoint representative of a complete (100%) loss of feedwater flow.

c. Startup bypass on conditions of reactor power greater than 25% full power for AMSAC will be l automatically removed. Manual actuation can be achieved by placing the channel in test.

d. AMSAC has no stated accuracy requirement.

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4. See Attachment 4 for DSS Logic, one-line, and Schematic Sketcbes, and . Attachment 5 for AMSAC One-line and Sc..ematic Sketches.

I. Identification of Snacific Power Sources and Recuire- i Ranta '

1. Safety related power supply is not required.

Operability during Loss of offsite Power is required.

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2. DSS

a. CRDM de-energization resulting from a LOOP will accomplish the intended function of DSS.

Thus DSS need not be supplied frna safety related sources. Supply of the DSS from safety related sources is permissible, providing that appropriate separation and isolation is maintained.

! b. FSAR Section 14, page 14-25 (Loss of All

• Power) 14.1.2.8.4.a) states "a loss of power

results in gravity insertion of the control rods and trip of the turbine valves."

3. AMSAC

a. Continued operability during LOOP dictates that AMSAC power be derived from safety related sources. The AMSAC equipment housed in the NNI cabinets receive vital and regulating sources. power The from both equipment housed in GM and EFIC are also powered from-battery backed vital sources. The battery backed vital source provides for proper operation of the AMSAC aquipment during a loss of offsite power.

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.,f J. Identification of Instrumentation and Recuiremanj;;g Refer to preliminary Bill of Material, Attachment 6, for dettiled items contained in the following equipme.nt.

a. NNI Cabinets X&Y

b. RSAE Cabinets A&B

c. CRDCS Cabinets

d. MCB TGR

'a. EFIC A&D See applicable codes and standards in Section A above for the requirements on DSS and AMSAC instrumentation.

K. Islantifica tion of Seecific Terminations for all Existine Electric Tie-ins

1. DSS - Inout/outeut List NNI-X

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2-5-1-1, 2&l8 Input from RSAE Cab. A (RC Press) 2-7-2-23&24 Output - CRD Enable 2-7-3-3&4 Output - CRD Trip 1 2-7-5-17 thru 20 Input - CRD Contacts for Test Lamps j NNI-Y

! 8-7-6-10,11&l2 Input from RSAE Cab. B

' (RC Press) 8-7-6-1&2 Output - CRD Enable 8-7-6-344 Output - CRD Trip 2 8-7-6-5 thru 8 Input - CRD Contacts for Test Lamp RSAE Cab._A TB5-4,5&6 Output to NNI-X (RC Press)

BSAE Cab. B TB5-4,5&6 Output to NNI-Y (RC Press) 8 A

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CRDcs De Mold sunniv Cabinet A (New Terminal Blocks)

TB14-1 thru 8 Input from NNI-X (Cnable &

Trip) and output to NNI-X (Indication)

TB13-1&2 Output to SER (Enable)

-344 Output to SER (Trip 1)

-5&6 Output to SER (Trip 1)

TB10-1 thru 10 AC PWR and SCR Row Trips TB12-1 thru 8 Input from NNI-Y (Enable &

' Trip) and output to NNI -Y (Indication)

TB11-l&2 Output to SER (Enable)

-344 Output to SER (Trip 2)

-5&6 Output to SER (Trip 2)

TB3-1 thru 10 AC PWR & SCR Row Trips Each SCR Cabinet 5A,6A,7A & Aux (A) TB11-5&8-Trip wires SIE - To be assigned

2. AMSAC - Innut/outnut List

, GM Channel A TB2 1,2&3 Output to NNI X(Neutron Flux Signal, 0-10v)

GM Channel B TB2 1,2&3 Output to NNI Y(Neutron Flux

! Signal, 0-10V)

NNI-X 2-9-5-13,14&4 Input from GM A (Neutron Flux Signal)

!. 2-9-3-7&8 Outnut to EFIC A (AMSAC Trip) 2-9-3-11,12,19420 Outpc? to Turbine MCB TGB

(AMSAC Trip i Cont.)

2-9-4-18&l9 Output to SER (Test Alarm) 2-9-4-20&21 Output to SER (Trip Alarm) 2-9-4-22&23 Output to SER (Trip Alarm) t i

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IDI.1-1 6-7-2-13,14&6 Input from GM B (Neutron Flux Signal) 8-7-2-7&8 Output to EFIC D (AMSAC Trip) 8-7-2-15,16,17&l8 Output to Turbine MCB TGR (AMSAC Trip) 8-7-2-19&20 Output to SER (Test Alarm) 8-7-2-21&22 Output to PER (Trip Alarm) 8-7-2-23&24 Output to SER (Trip Alarm)

EFIC A TBD7-9&lo Input from NNI-X (Trip)

TBE2-7&8 Input from Isolator EFIC D TBD7-9&lo Input from NNI '/ (Trip)

TBE12-7&8 Input from Isolator MCB TGR o

TB15-17&l3 Input from NNI-X (Trip)

TB15-19620 Output to NNI-X (Confirm)

T515-21&22 Input from NNI-Y (Trip)

TB1!-23&24 Output to NNI-Y (Confirm)

SIB - To be assigned L. Preliminary Safety Analysis See Modification Safety Evaluation, Attachment 7.

Preliminary safety analysis indicates a potential for Technical Specification change. Engineering Project Manager must inform Nuclear Licensing and the site Project Manager.

M. ALARA Criteria and Accreach Not Applicable 10

i '<' N. Environmental Qualification Tmnlicatiens

1. Florida Power Corporation's Environmental and Soissio Qualification Guide Specification and Data SP-5095 Zone #13 Elevation 145'- 0" specifies the environmental conditions at the SER, NNI, and MCB TGR locations. The environmental conditions ares Temperature 70-80 0 F L Radiation 1x104 Rad - 40 year Total Integrated Dose e

2. Zone #43 Eleve. tion 108' 0" specifies the environ-mental conditions at the RSAE Cabinets and Zone f58 Elevation 124'- 0" for the CRD Cabinets, EFIC, 4

and GM. The environmental conditions are the same

] for Zones (43 and 58 and are:

Temperature 70-800 F i

_ Relative Humidity 40-6g%

Radiation 1x10 Rad - 40 year Total Integrated Dose O. Fire Plan Imolication Not applicable i

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i l d II. Total Proiact Scene and Work Breakdown A. General Total Proiect Scone .

1. Detailed Design Package (MAR)

a. Desiy.t Development

b. Site visits

c. Verification

d. Project Cost Estimate & Schedule

, 2. Purchase Equipment

a. Bailey

b. Grayhill

c. Vitro

d. Dialight

e. Potter & Brumfield ,

f. MMIS

3. Conduit Hangers

a. Evaluation of old

b. Design New i

c. Manufacture New

d. Install New

4. Conduit Installation

5. Cable Installation

6. Fabricate Test Switch Module

7. Fabricate Test and Relay Panel for CRDCS

8. Install DSS Equipment & Wiring ,

a. RSAZ Cabinets A&B t

b. NNI Cabinets 2,3,5,7&S

c. CRDCS DC Hold Supply Cabinet A and SCR Pover Supply cabinets t

9. Install AMSAC Equipment & Wiring ,

a. NNI Cabinets 2,3,5,6&a

b. MCB TGR Panel i

c. EFIC Cabinets A&D -

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10. Terminate Cables for DSS

a. RSAZ Cabinets A&B (to NNI 248)

b. NNI Cabinets 2&8 (from RSAE A&B and to CRDCS)

c. CRDCS DC Mold supply cabinet A (from NNI 248 and to SER)

d. SER (from CRDCS)  !

11. Terminate Cables for ANSAC

a. GM Channels A&B (to NNI 2&8)

, b. NNI Cabinat 2 (from GM A and to MCB TGR, EFIC A and SER) c.

NNI Cabinet 8 (from GM B and to MCB TGR, EFIC D and SER) i

d. MCB TGR panel (from NEI 2&B)

e. EFIC A (from NNI 2)

f. EFIC D (from NNI 8)

g. SER (from NNI 2G8)

12. System Testing

a. DSS

b. AMSAC

13. Final As-Built Drawings [

14. Instruction Manual Updatos

15. Project Closecut i

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3. Detailed Eneineerina scene

1. Tasks and outputs

a. MAR Package (A/E) ,

(1) Administrative and Technical Support  !

Information. I i

(a) Transmittal Memo (b) MAR Form I (c) Project Assignment Memo (d) Design Data Sheet (e) Design Input Record >

(f) Correspondence Related to Design (2) Design Support (a) Verification Report (b) Analysis / Calculation Sheets  !

(c) Engineering Study (d) Work order '

(e) REI Form '

, (f) Data Transmittal sheets '

(3) Installation, Examination, Test & ISI Requirements (a) Engineering Instruction (b) Interim Drawings (c) MAR Sketches (d) Cable Pulling and Data Sheets l (e) Cable Termination and Test Data  !

Sheets  :

(f) Bill of Materials (g) Vendor Information  ;

(4) Reference Material i (a) Reference Drawings  !

(b) Procurement Requisitions / Purchase  ;

orders  :

b. Interface with A/E (1) St. Petersburg Engineering, I&C (80%)

and Electrical (20%)

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c. Review and Approval of MAR Package (1) St. Petersburg Engineering, I&C (80%)

and Electrical (204)

d. Interface With Site Engineering  !

(1) St. Petersburg Engineering, IAC (80%) :

and Electrical (204) {

, e. Interface With Plant Engineering (1) St. Petersburg Engineering, I&C (80%)  ;

and Electrical (20%) .

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2. Interim Drawings  :

a. DSS 1 i l (1) RSAE A&B j E-201-337

, 55-211-047, RC-I i B-205-019  !

! Equipment Lists & Bill of Materials i i

(2) RSAE A i

EC-210-746 l j EC-210-747 212's

) (3) RSAE B (

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EC-210-749 I EC-210-750 t 212's

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(4) NNI D4034033 Sh. S&J D8034013 D4034044 D8034023 08034042 Sh. 243 i Module Arrangement List Cab. 3 Row 344 Cab. 5 Row 3&4 Cab. 7 Row 344 Cab. 7 Row 5&6

, EC 209-174 Sh. 1&2 4 EC-209-179 Sh. 2 (5) CRDCS EC-209-024, DR-15 55-211-024, DR-22 707101-1253 707091-1255 707100-1049 707083-1032 707356-1248 703007-1257 212's (6) SER B-204-024 RIS B-1013-586 Sh (no. to be determined)

EC-209-168 l b. AMSAC

l (1) Gamma Metrics f

SS-211-042, NI-25 55-211-042, NI-24 209-042, NI-03 209-042, NI-04 212's i

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(2) NNI D8034042 Sh. 2&3 (identified above)

, D8084034 Sh. 1,2,344 D8034017 D8034021 IC-209-178 Sh. 2 (identified above)

EC-209-179 Sh. 2 (identified above)

Module Arrangement List Cab. 3 Row 3&4 Cab. 5 Row 3&4 Cab. 6 Row 344 (3) ETIC 3801-3003 Sh. 142 3801-3008 Sh. 4&7 3801-3005 Sh. 1 3801-3021 Sh. 1 EC-210-769 i EC-210-773

! SS-211-026 Sh. EF-I3 & EF-22 212's

, (4) MCB TGR B-208-057 Sh. TB-20 EC-210-051 1 EC-210-052 E-201-135 55-211-057 Sh. TB-20

, Equipment List and Bill of Material for l TGR j

(5) SER I

B-204-024 RIS B-1013-586 Sh (no. to be determined)

c. DSS & AMSAC Conduit 224-103 Sh. 35,36,4:.224,63 & 170 E-215-031 Sh. 2 E-215-032 Sh. 2&3 E-215-033 Sh. 1 17 i

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3. New Drawings

a. DSS (1) CRDCS EC-209-024,DR-15A EC-201- For test and EC-210- relay panels and trip box

b. AMSAC (1) NNI D8034034 Sh. 5 (2) EFIC (Existing Vitro drawings -

New FPC release) 3801-1123 3801-1124 o

0423-2645 i 4. Revised Specifications None

5. New Specifications None

6. Analysis

a. Seismic & Environmental (1) RSAE Cabinets A&B (2) EFIC Cabinets A&D (3) GM Cabinsts A&B

b. Calculations (1) Time Delay Calculations for DSS & AMSAC (2) Accuracy Calculations for DSS 18

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7. Trips

a. CR-3 Site (1) Detail Design Development (a) One Engineer from A/E (b) One Engineer from St. Petersburg or Site Engineering (2) Confirmation Walkdown i (a) One Engineer from A/E (b) One Engineer from St. Petersburg Engineering (c) One Engineer from Site Engineering (d) One Engineer from Plant Engineering (e) operations Personnel (f) Maintenance Personnel (g) Training Personnel

8. Assumptions

• a. CRD safety groups 1,2,3 and 4 will not be tripped by the DSS.

b. DSS and AMSAC test and trip status will not be input to RECALL /SPDS or the plant annun-ciator.

c. The NRC review, approval, and/or comments on the B&W owners Group "Design Requirements for DSS and AMSAC" (B&W Document 47-1159091-00) will not change the requirements of that document or any work done for the conceptual design.

d. The mass and thermal loads added by the new I

equipment will be within the qualification envelope of the ET:C system, RSAE cabinets, and GM channels.

e. It is assumed that the wide range RC pressure transmitters RC 158-PT and RC 159-PT will be calibrated for a 0-3000 psig range by another MAR.

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f. It is assumed that the GM Channel A will be added by another MAR.

g. It is assumed that if the time delay and accuracy requirements cannot be met that the setpoints will be set as not to violate the analysis.

9. Exclusions None

10. Deliverables

a. Complete MAR Package

b. Project Cost Estimate and Schedule l

c. Seismic and Environmental Analysis

d. Time Delay and Accuracy Analysis C. Installation Work Breakdown

. 1. Outage /Non-outage

a. Outage (1) Install DSS Equipment (See II.A.8.)

(2) Install AMSAC Equipment (See II.A.9.)

(3) Terminate Cable for DSS (See II.A.10.)

(4) Terminate Cable for AMSAC(See II.A.ll.)

(5) System Testing for DSS and AMSAC

b. Non-outage l

' (1) MAR Package (See II.A.1) i (2) Purchase Equipment (See II.A.2) l (3) Conduit Hangers (See II.A.3) i (4) Conduit Installation (5) Cable Installation (6) Fabricate Test Switch Module (7) Fabricate Test Panel for CRDCS l '

(8) Final As-Built Drawing (9) Instruction Manual Updates (10) Project Closecut 20

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2. Safety /Non-Safety

a. Safety (1) MAR Package (a) Interfaces with Safety Systems only (See I.G)

(2) Purchase Equipment

' (a) Vitro (b) Safety related MMIS items (See Bill of Material (3) Install DSS Equipment in RSAE Cabinets A&B (4) Install AMSAC Equipment in EFIC Cabinets A&D (S) Terminate Cables for DSS in RSAE Cabinets A&B (6) Terminate Cables for AMSAC int (a) GM Channels A&B (b) EFIC Cabinets A&D (7) System Testing DSS (a) RSAE Cabinets A&B (8) System Testing AMSAC (a) GM Channels A&B (b) EFIC Cabinets A&D (9) Final As-Built Drawings j (a) DSS See II.B. 2. a .1,2 & 3, and II .B. 2. c i

(b) AMSAC 2

See II.B.2.b.1,&3, II.B.2.c, and II.B.3.b.2 21

5 i .I (10) Seismic and Environmental Analysis

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(a) RSAE Cabinets A&B (b) EFIC Cabinets A&D (c) GM Channels A&B

b. Non-Safety (1) MAR Packags (a) Everything except interfaces with safety systems (See II.C.2.a.1)

(2) Purchase Equipment-(a) Bailey (b) Grayhill (c) Dialight (d) Non-safety MMIS items (See Bill of i

Materikl)

(3) Conduit Mangers (See II.A.3)

(4) Conduit Installation (5) Cable Installation (6) Fabricate Test Switch Module (7) Fabricate Test and Relay Panel for CRDCS (8) Install DSS Equipment and Wiring (a) NNI Cabinets 2,3,5,758 j

(b) CRDCS DC Hold Supply Cabinet A and SCR Power Supply Cabinets (9) Install AMSAC Equipment and Wiring l

1 (a) NNI Cabinets 2,3,5,648 l (b) MC5 TGR Panel I

(10) Terminate Cables for DSS (a) NNI Cabinets 2&8 (b) CRDCS DC Hold Supply Cabinet A (c) SER 22

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(11) Terminate Cables for AMSAC (a) NNI Cabinet 2&8 (b) MCB TGR Panel (c) SER (12) System Testing DSS (a) NNI Cabinets (b) CRDCS DC Hold Supply cabinet A (c) SER (13) System Testing AMSAC (a) NNI Cabinets (b) MCB TGR Panel (c) SLR (14) Final As-Built Drawings (a) DSS (1) II.B.2.a.4,5&6 and II.B.3.a.1 (b) AMSAC (1) II.B.2.b.2,4&5 and II.B.3.b.1

3. Craft

a. Electrical (1) Conduit Rangers (2) Conduit Installation (3) Cable Installation (4) Terminate Cables for DSS (5) Terminate Cables for AMSAC

b. I&C (1) Fabricate Test Switch Module (2) Fabricate Test and Relay Panel for CRDCS (3) Install DSS Equipment (4) Install AMSAC Equipment (5) System Testing 23

i I Y 4. Plant Area Modifications will be made in the following plant areas:

See conduit layout skatebes, Attachment 8, for layout for areas a,c,eag.

i (a) RSAE Cabinets A&B Control complex elev. 108' 0" 4160V ES SWGR Rooms A&L i (b) NNI Cabinets 2,3,5,6,748 Control complex elev. 145' 0" control Room (c) CRDCS Cabinets Control complex elev. 124' 0" CRD Room (d) SER 4

Control complex elev. 145' 0" Control Room 3 (e) GM Channels A&B Control complex elev. 124' 0" 480V SWGR Rooms A&B (f) MCB TGR Panel Control complex elev. 145' 0" Control Room (g) EFIC Cabinets A&D Control complex elev. 124' 0" EFIC Rooms

5. Controlled Work Area /Non-Controlled Work Area All work to be done is in a controlled work area.

6. High Radiation Zone /Lov Radiation Zone All work to be done is in a low radiation zone.

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ATWS CONCEPTUAL DESIGN i.! <

Attachment 1 055 Layout

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Cabinets

2. Output 0-10VDC represents 0-3000 psig.

3. Will be refer-enced to NNI signal common.

NNI Cabinets Trip & Enable Contacts 1. Contact rating, to CRDCS DC Hold supply 120VAC, 2 amp Cabinet A minimum.

CRDCS Dc Hold Test & Confirm contacts 1. Contact rating, Supply Cabinet A for NNI lamps 120VAC, 1 amp minimum.

. 2. To light high brightness neon lamps.

Test & Confirm contacts 1. Contact rating, for SER input 125VDC, 1/2 amp minimum.

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NNI Cabinets EFW Actuation Contacts 1. Contact rating, to EFIC 120VAC, 1 amp minimum.

EFIC Cabinets EFW Actuation Digital 1. Qualified Digital A&D Signal Isolation inglation device (1E to lE).

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120VAC applied is low resistance output.

3. Output resistance low /high compat-ible with EFIC logic.

NNI Cabinets Turbine Trip Relay 1. Contact Rating, Contacts 120VAC, 2 amp minimum.

Test and Confira 1. Contact Rating, Contacts for SER 125VDC, 1/2 amp input minimum MCS TGR Turbine Trip Relays 1. Coil, 120VAC, 1 amp maximum.

2. Contact Rating, 125VDC, 2 amp inductive minimum (actuated device zener-zener

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BILL OF MATERIAL alLL OF MATERIAL s REV. SHEET I OF 5 MAR. NO. 84-06-07-01 FCN HO. FCR NO. WORK REQUEST NO- DATE REQUIRED ITEM SAFETY ITEM DESCRIPTION QUANTITY DATE MM481REEQUISITION NUMaER NUMBER CLASS ONCLUDE DESIGN CODElCLASS) Ull REQUIRED (P.R.iMMIS SINPA)

YIN QTY 1 PE Triple DC Signal Generator 4ea WA 63705114 Bailey P/N 6623835-3 2 NS Sicpal Monitor M 6ea WA 63705687

• Bailey P/N 6623819-1 g 3 PE 24VDC Auxiliary Relay 6ea M

WA 52600057 q Bailey P/N 6624913-1 y 4 PE Two Input Auctioneer 2ea

?

WA 63705316 o Bailey P/N 6624523-1 0 5 16 'Ihree Position Test Switch 5

4ea PR (Grayhill) z Grayhill P/N 44L45-03-2-3S

• 6 16 ht Iany, Neon Cartridge, Red ICea PR (Dialight)

Dialight Corp. 507-4537-0931-673 9 7 f6 ht Ianp, Neon Cartridge, Yellow 11ea IR (Dialight) $

Dialiglt Corp. 507-4537-0936-673 o, 8 16 Test Iany, Neon Cartridge, hitite 10ea PR (Dialight)

Dialight Corp. 507-4537-0935-673 9 16 Ianp Holder 31ea PR (Dialight)

Dialight Corp. 250-7445-14-504 FPC ENGINEER (PM) Y. M [048 .__._ ORIGINATOR STP MATERIALS PHONE/ (f 3]_Edddd2f PHONE [ibfNfSM/03 SITE PHONE DATE DATE _/o/A M d( CONSTR DATE RETURNED

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s:LL OF MATERIAL s REV. SHEET OF MAR. NO. 84-06-07-01 FCN NO. FCR NO. WORK REQUEST NO- DATE REQU4 RED D. STOCK ITEM SAFETY ITEM DESCRIPTION OUANTITY DATE MMISf REEQUISITION NUMBER NUMBER CLASS (INCLUDE DESION CODE J CLASS) Ull YIN OTY REQUIRED (P.R. I MMIS 5 i NPA) 10 PE Relay, P&B PRDAllA7A 2ea PR (Potter & Brunfield) 11 16 Relay, Clark 5U12-76 2ea WA 62840709 >

d 12 NS Relay, Clark 5U8-76 4ea WA 62840693 o

13 NS Pushbutton, Momentary (N.C.), 2ea PR (Grayhill)

Grayhill P/N 10-101 [n m

14 NS Fuseholder, Indicating, Bussnan 2ea WA 01265683 E HKIeX o m

15 PE Fuse, Slo Blo, Ikassnan IOX-5 2ea WA 01280409 y 16 NS Terminal Block, Kulka 602-JJ-10-F 6ea WA 65230743 h 17 S Voltage to Voltage Isolator 2ea WA 52601302 1

Foxboro IN-2AO-VAI w/ opt 0-10VDC h

18 S EFIC Digital Isolator, 120 VAC 9 2ea WA 52601210 -t Vitro 40423-2645-4 m 19 S Misc. EPIC Wire & Acces.

I/C cable, 22AWG Mil-W-22759 200ft PR (Vitro)

Wire Lug, T&B RAF 853 or equal 4 Wire IAng, T&B RAT-863 or equal 4 Wire Sleeve, .06S I.D. Sft FPC EN INEER (PM) N. (oca ORIO1NATOR I STP MATERIALS PHONE I$E_% L . - SD f PHONE hYb 3ET~b"5 SITE PNGNE DATE DATE /o/.28/d( CONSTR DATE RETURNED em n, n . , - - . .

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stLL OF itATERIAL s REV.

BILL OF MATERIAL SHEET OF MAR. NO. 84-06-07-01 FCN NO. FCR NO. WORK REQUEST NO- DATE MEQUIRED D.S E K ITEM SAFETY ITEM DESCRIPTION QUANTITY DATE MMISiREEQUISITION NUMBER NUMsER CLASS (INCLUDE DESIGN CODElCLASS) UJl YlN QTY REQUIRED (P.R.f MMIS alNPA) 20 PE Module Frame 4ea IR (Bailey)

Bailey P/H 6629506-1 21 16 Module Connector, 36 pin 2ea IR ($niley) h Bailey P/N 1945304-2 (ElcO) "

8 22 16 Fastener Stud 8ea IR (Bailey) M Bailey P/N 197285-1 !U M

23 PE Brg, Wisher 8ea PR (Bailey) #,

Bailey P/N 197296-8 c, C

24 PE Retaining Ring 8ea PR (Bailey) 5 Bailey P/N 197301-18

• 25 NS Cable Clip 8ea PR (Bailey)

Bailey P/N 1943187-6 .

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9 26 NS Module Receptacle, 32 pin 2ea PR (Bailey) $

Bailey P/N 69035-1 (Blue Ribbon) 4 cn 27 NS Module Connector, 32 pin 2ea PR (Bailey)

Bailey P/N 691371-1 (Blue Ribbon) 28 16 0.112-40x0.25 IE CD PL.STL PAN 4ea PR (Bailey)

ID SEMS. EXT FPC ENGINEER (PM) [.M. Low ORIGINATOR kMI STP MATERIALS PHONE {yll).S$6 ~SM PHONE ($00NT-2/03 SITE PHONE DATE DATE /? N T/#i CONSTR DATE RETURNED

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s:LL OF MATERIAL s REV. SHEET OF MAR. NO. 84-06-07-01 FCN NO. FCR NO. WORK REQUEST NO- DATE REOutRED ITEM SAFETY ITEM DESCRIPTION QUANTITY DATE MMISiREEOutSITION NUMBER NUMBER CLASS (INCLUDE DESIGN CODEiCLASS) UfI YfN OTY REQUIRED (P.R.IMMIS 8iNPA) 29 16 Screw, Mach 2-56x1/2" Flat Head 4ea IR (Incal)

CAD, PLT, SIL p m

30 16 Inckwasher Int. 82 ID, CAD PLT 4ea PR (Incal) g E $

31 16 Hex that, 2-56, CAD PLT, SPL 4ea PR (Incal) 32 }E Cable Clip Ilardware 10-32x1/2" CAD SS FLT 10 8ea 01710491 h 10-32 SIL Hex that 8ea 01150512 -

810 Plain msher 8ea 01150010 E 33 ts Cable EK-18W, I/C 14 AWG. BIK 400ft WA 01270419 >

d 34 PE Wire Iog, Ikarndy YAE 12-N 100ea WA 01267852 N I

35 16 Wire Sleeve 20 ft h

36 NS Wire, 22 Solid Mil-W-76B, BLK 2000ft WA 01270329 37 S Wire I/C,14 AWG, SIS, Red . 30ft WA 01270360 38 S Wire, I/C, 14 AWG, SIS, GRN 30ft WA 01270361 39 S Wire Lug, 120-14, 6-8 Stud 1 box WA 01267874 FPC EN NEER (PM) df/* bo ORIGINA R M ..

STP MATERIALS PHONE /M.866_ -f325 PHONE f M ff-DA7 SITE PHONE DATE DATE_Z d SA CONSTR DATE RETURNED

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BILL OF MATERIAL asLL OF MATERIAL s REV. 5 o, 5 SHEET MAR.NO. R4-06-07-01 FCN NO. WORE REQUEST NO. DATE REOutRED ITEM SAFETY ITEM DESCRIPTION QUANTITY RECMD. STOCK DATE MMISi REQUISITION NUMBER NUusER CtASS pe6CLUDE DESIGN CODE i CLASS) Ull Y#N QTY REQU4 RED P.R. i MMIS 5 i MPA) 40 PS Cable, EK-35A, 2/C, 14 AWG. BLK 2500' WA 01270427 41 15 Cable, EK-18E, S/C,14 AWG, BLK 400' WA 01270417 42 IS Cable, D$-18J, 9/C,14 AWG, ILK 435' WA 01270396 h S

43 16 1-1/2" Corduit & Assoc. Fittings 350' 44 PS 1" Conduit & Assoc. Fittings 600' '-

45 16 AL Pt& Approx.10"x19"xl/8 M

Make from 01574117 $

46 PE AL Pt& Approx. 10"x24"x1/8" $

47 16 Relay, P&B P/N RIO El 120VAC 27E461 8 ea IR (Potter & Brumfield) 48 !S Terminal Block, Kulka P/N 37TB-16 N 8 ea WA 65230754 5 49 IS E

!!uffunn Box P/N A-808SC 4 ea PR (thaffman)

FPC ENON8EER(PM) d.M./N- ORIOINAT ST9 MATERIALS FHONE $5fD SSS-S.52T PHONE eY ~ElO3 SITE PHONE DATE REC 4*D.

DATE DATE N/f3/8( CONSTR DATE RETURNED

ATVS CONCEPTUAL DESIGN ATTACHMENT 7

.. uCOIFICATION SAFETY EVALUATION Sheat 1 of 2'

MAR NO. 84. 06. 07 . 01 i f SAFETY EVALUATION: Answer the following questions and provide specific just!!! cation

'r' (use attachment if necessary).

(. Is the abability of an occurrence or the consequence of an accident or malfunction of Important to safety as previousJy evasusted in the Final Safety Analysis Report. INCREASED 7 YES _ , NO ,,X,,

. secausee

~

See Attached Sheet

2. .ls the gesalbility for an accident or malfunction of a different type than any previously evaluated in the Final Safety Analysis Report, CREATED 7 YE5_ NO X,,,,,

Because See Attached Sheet - -

,h ,

3. Is the margin of safety, as defined in the beats for any Technical Specification, ,- ,

REDUCED 7 YES _ NO X Becauses-

-.. .. See Attached Sheet

. ; ~, .

- UCENSE REVt510N REQUIRED: Final Safety Analysis Report: YE5 X NO ,, ,

• Technical Specification: YES T NO ,

• - NRC Authorization for Change Required: YES NO _

Semi Annual Reporting to NRC Required: YES No _

,[,

, 10CFR30.39 CHECKUST ,

• Does the proposed action change the Fina15afety Analysis ..

. Report or require additional description to be added to the Ftnal Safety Analysis Report?- *

. YES ( X) NO( )

Notify Manager, Nuclear Ucensing ir

. and Fuels Management - 3, w

t -

+ -

- Is a Change to the Technical '

Specifications Required?

YES ( X) 1r NO( )

w

- Is any unreviewed safety question involved, i.e., *

(1) is the probability of an occurrence or the consequences of an accident, -

t ,

or malfunction of equipment important to safety previously evaluated in

- the Safety Analysts Report increased? YF3.,,, NO (2) Is the possibility for an accident or malfunction of a'7dferent type than any previcualy evaluated in the Safety Analysis Report created?

YE5 NO

<; (3) to thd7nargin Tsafety, as defined in the basis for any Technical Specification reduced? YES ,,,,, NO

~

Any answer YES ( ) h All answers NO - ,

u Request and receive NRC Authorization for change 9r Document Change includings (1) Description of change (2) Written Safety Evaluation which provided basis for items (1) (2), and (3) above.

Authorization Received ( ) Description Safety Evaluation Complete h E Initiate Installation of Modification

• Required changes to Technical Specifications Prepared by N 8 should be processed in parallel to this checklist. Name Date

v-ATTACHMENT 7 Shee2 i of 2

' i

,: ATWS CONCEPTUAL DESIGN MODIFICATION SAFETY EVALUATION

1. No, the utilization of a DSS trip provides a diverse trip actuation to the control rod drive SCR's. The DSS is a redundant backup to the Reactor Protection System trip functions. The AMSAC provides a trip sigaal to the turbine and EFW initiation on a two-out-of-two trip. DSS and AMSAC are physically and electrically isolated from protection systems.

2. No, the DSS provides a backup trip function, of the RPS, to the SCR's. The AMSAC provides a trip' signal to the turbine and EFW initiation. None of these are different than evaluated in the FSAR.

3. No, the DSS trip is a backup to the RPS trip and the AMSAC does not reduce the margin of safety as it is a mitigating system.

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ATWS CONCEPTUAL DESIGN i l i- Attachment 8 Sheet 1 of 3 Conduit Layout w

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i .f TRIP REPORT # Q4IE 4/10/86 e

TRIP REPORT AUTHOR: B.J. Shepherd FILE NO. MSS-7[77 4 QBGANI2ATION VISITED: Florida Power Corp. COPIES LOCATION: Crystal River Unit 3 DATE OF TRIP: 4/3/86 PURPOSE: A'IWS Conceptual Design Walkdown i PERSONNEL ATTENDING:

B.idi U.C B.J. Shepherd Ron Carbiener Paul Fleming Ed Good W.A. Stephenson Jack Tunstill Hugh Gelston

, R.H. Low Ray Whittman Rick Currier The Conceptual Design Walkdown for the Diverse Scram System (DSS) and ATWS Mitigating System Actuation Circuitry (AMSAC) was conducted on April 3,. 1986. The design for DSS & ANSAC was reviewed with the above personnel. During the walkdown it was determined that the NNI System drawings identified some Module spaces & terminals as spare when modules were already installed and wires existed on terminals.

Where required the location of DSS & AMSAC Modules will be changed in the Conceptual Design to unused module spaces.

For terminals shown as spare where wiring exists, it should be determined if the wiring can be removed from the system.

FPC Personnel desired to further review the DSS & AMSAC design prior to answering question numbers 16 and 17 on the walkdown check list. It is anticipated that FPC's review will be complete by 5/5/86.

The draft DSS & AMSAC Conceptual Design is being routed to FPC Personnel for comments. It is anticipated that FPC comments will be trans:. teted to B&W by 5/5/86. Upon receipt of comments B&W is to review and resolve the comments, revise the Conceptual Design Draf t and issue the Final Conceptual Design Package.

t-

DESIGN WALKDOWN CHECKLIST i

e !9 Florida P. o. . .w. .e. . .r.

. Crystal Rivet Unit No. 3

._ s, . o . .. o .

84-06-07-01 ATWS 4/3/86 6

ATWS Conceptual Design O Conceptual O confirmation PARTICIPANT'S NAME (Pfesse Print) FIRM & DEPARTMENT TELEPHONE Ron Carbiener FPC N . O . M .' 4456 Ed Good FPC Nuc. Licencing 4602

' Jack Tunstill FPC Nuc. Licencing 4691 R.H. Low FPC Nuc. Engineering 5325 Paul Flerning FPC Nuc. OPS. Trng. 795-0504(126)

W.A. Stephenson FPC Nuc. Plant OPS 4171 Hugh Gelston FPC Nuc. Plant Engr. 4397 Ray Wittman FPC Nuc. Plant OPS 4184 Rick Currier FPC N.O.M. 4406 B.J. Shepherd BW Plant Engr. Services (804)395-2777 WALK 00WN INSTRUCT 10NS

1. The Design Engineer is responsible for notifying the FPC Engineering Project Manager to arrange design walkdowns.

2. The FPC Engineering Project Manager is responsible for arranging all necessary access clearances and notifying site walkdown attendees.

3. The Design Engineer is responsible for preparing the Design Walkdown Checklist (to os corr.pleted fully

-N/A in advance as appropriate) and for recording walkdown observations on the Observations page.

4. Each observation should be clearly identified including location suen as, building, room number, elevation, plant coordinates, etc.

5. Clarifying photographs or sketches should be utilit.ed when appropriate.

6. Individual observations should not be lumped into single entries.

7. An appropriate contact person for follow.up should be identified.

8. The Design Engineer is responsible for the resolution of all observations.

9. Coples for earlier walkdown checklists with attachments shall be provided for subsequent walkdown reference.

. 5?5s'

WALKDOWN QUESTIONS SECTION A (Complete for Conceptu-l and C'nfirmation Walkd wne)

Stt i

7 QUESTION ns o ,,,4 **"[,,

,, 7 1 Are there special work area access problems? (Bulky or heavy equipment, limited access of work spaces, etc.) c gC 2 Do work areas require special considerations for construction, operation, or maintenance? (Respirators, temporary work enclosures, radiation access, security, special v.ork permits or clearances.) kO O h 3 is there need to remove temporarily gratlng handralls, structural steel, condult, tubing, piping, supports, equipm9nt, or instruments to facilltate final Installation? O kO 4 is there need to remove permanently grating, handralls, structural steel, conduit, tubing, ploing, supports, eQuloment, of Instruments to facilitate construction? O % C 5 Do design or work complexitles require special Installation, or testing

- ' procedures? (Special vendor Installation requirements, special lif ting facilities.

- interferences removal, etc. for maintenance.) NO O 6 Do unrelated modifications affect the work areas creating potential interferences? )Q O O 7 Will temporary shielding be recuired? O % C r* -

8 - Will permanent shielding be required? O N O 9 Will the design increase radiation / contamination levels? O % 0 10 Will the design increase radiation / contamination soread? O M C _

11 is instrumentation / operating equipment located to minimize Installation and operating corsonnel exposure? %C C 4

. 12 Are alternate designs feasible to reduce potentlat exposure? O $ 0 13 Does the anticipated routing (conduit, tray, piping, tubing) exhibit the clearest a route relative to Installing succorts, restraints. etc.? MO O (5J 14 Does the design provide for efficient maintenance of existing equipment / system? %O O $P 15 Does the design orovide for efficient maintenance of new equioment/ system?  % O O' (7) 16 Does the design provide for efficient operation of existing eauloment/ system? O O O (9) 17 Does the design provide for efflelent coeration of new equiement/ system? O O C @

18 ~ Does the design provide for efficient testing of existing equipment / system (on line callbration of instrumentation feasible)? YO O 'Q 19 Does the design provide for efficient testing of new equioment/ system? %C O f/ /)

20 Does the design provide for efficient ISI of existing equioment/ system? O Q  %

21 Does the design crovide for efficient ISI of new eculoment/ system? O O X 22 Are flammable materials being added to the area? O X C 23 Does design impact Accendix 'A' requirements? ;X C O "(/p 24 Does the equioment being installed / altered increase fire hazards in the area? O  % C _

25 If the equipment is safety related, do fire hazards exist in the area which may (moalf its operability? O IO _

26 Are fire barriers being breached by the design? X O O 63) 27 Are security barriers being breached by the design?  % C C_

28 If safety related,is new equipment located in proximity to high energy pipe whose failure could impair operability due to pipe whip,let Impingement, pressure or temocrature conditions? O NO 29 If new equipment is a high energy system, Is It located near safety related equipment whose operability could be Impaired due to failure of the new equipment? O O N ici .i Pett 8 ef 6

ses Y QUESTION ves i.o ,4 ***El47 J 30 if the new equipment is safety related, are there existing non seismic items located such that their failure could Impalf the new eculomont's safety function? O MC 31 If the new equipment is non seismic, could its failure impair adjacent safety.

related eculement functions? O M O 32 Have adequato measures been taken to maintain required separation between redundant equipment? kO

'T C O h 33 Are existing structures adequate for support of new eculoment? '

O . (/V f) 34 Has all adjacent equipment been Identifled to allow for answers to all of the .

questions? %O O SECTION B

,(Complete for Confirmation Walkdown only)

Set Y QUESTION ves i,o =a Y'[e7 35 Are all temporary removals of grating, handrails, structural steel, condult, tubing, piping, supports, equipment or Instruments identifled on Installation drawings? O O O 36 Are all permanent removals of grating, handrails, structural steel, condult, tubing, piping, supports, equipment, or Instruments identified on Installation drawings? O O O -

37 Do Installation drawings clearly define locations based on dimensions from existing physical oblects? O O O

. 38 Does design provide approorlate tolerances? O O O 39 If modification deals with changing control board, were human factors considered? O O O 40 Are there existing holes In the floors or walls to allow devices to be passed through? O O O N! h0h 8ese 3 +# 4

WALKDOWN CBSERVATION

. . (.,BSERVATION RESOLUTION no. me. (Attach sketch if requiree _ Attath

( sketch if required) i  !

1 2 Clearance & work permits will be required for work in:

NNI System Cabinets, Remote Shutdown Aux. Equipment Cabinets, Gama Metrics Equipment Boxes EFIC System,

' Events Recorder Cabinets and Main Control Board TGR.

2 5 Special testing procedures will be required to verify the A W S DSS &

AMSAC equipment operation after installation. .

3 6 MAR's for RG 1.97 and Bailey "BY" transmitter replacement will be installed at the same time as this modification. Coordination of modi-fication installation to enable access to equipment cabinets will be re-

• quired.

4 11 Equipment for this modification will -

be installed in existing equipment cabinets located in the control com-plex. Radiation exposure to person-nel is therefore minimized.

5 13 Conduit routing has been chosen which provides for minimum effort in in-stallation of conduit & supports.

4 6 14 The design does not change the main-tenance efficiency of the existing systems.

7 15 The design utilizes modular type components which can be replaced with minimum work effoe't.

8 16 RH low to provide response by 5/5/86 e.".'ll$

FTALKDOWN F BSERVATION was m CSSERVATION RESOLUTIO:]

asa na (Attach sketch if required) (Attach sketch if resulted) i .?

9 17 RH Low to provide response by 5/5/86 10 18 The design provides for easy check of the bistable trip setpoints.

11 19 The design has built in capability for testing of bistable trip setpoints and +, rip actuations. Bypasses where required during testing are automat-ically implemented during testing.

12 23 Isolation .. *** remote shutdown system is accoe.p.' - . . "oh Foxboro safety gr^de

• eit2ge/ voltage isolation module <,.

13 26 Conduit must pass through existing .

& fire and security barrier walls.

27 14 32 Safety grade Foxboro V/V isolation '

modules are used to isolate signals between the remote shutdown aux.

equipment cabinets and the NNI system cabinets.

Safety grade digital isolators are used to isolate signals between the

.NNI system cabinets and the EFIC system cabinets.

15 33 Existing cabinets have space to support the addition of the new equipment.

.gEi c

WALKDOWN f SSERVATION

. . OSSERVATION RESOLUTION

o. me. (Attach sketch if reevired) (Attach sketch if roeulted)

<- 15 33 NNI system drawings identified The 055 modules originally planned for locations 3-5-5, 3-5-6, and 3-5-7 as these three locations will be relocated spare module locations. Equipment is to positions 5-3-13, 5-3-14, and 5-3-15.

already installed in these locations.

To enable the above location change.

AMSAC modules were relocated as follows:

From o T_o, 5-4-9 3-3-12 5-4-13 5-4-12 5-4-15 5-4-14 5-3-15 5-4-15

, NNI system drawings identified the . Determine if wiring is required for following teminal board terminals as system functions or if it is no longer spare. However, wiring exists on required and can be removed. .

these teminals.

8-7-6-l' thru 12 2-9 7 & 8 2-9 11, 12, 19 & 20 2-9 18 thru 23 2-9 13 & 14 1

4

DESIGN DATA SHEET g

Crystal River Unit 3 SHEET 1 OF 2 ao ,,ua o.,,

8 4 - 0 6- o ) - o \ jd'zg/g6 RTvJ S - O S S lE W S1% (L., SV STE ms q SAFETY CRITERI A: O Safety Listing Rev. Dated Page 2 Safety Classification Review Form (attach copy)

SAFETY RELATED: E Yes O No ens i.o APPLICA8LE DESIGN INPUT REQUIREMENTS:

1. liC O Basic functions of each structure, system and component.

. 2. K O Performance requirements such as capacity, rating, system output.

3. 3 O Codes, standards, and regulatory requirements including the applicable issue and/or addenda.

4. 3 O Design conditions such as pressure, temperature, fluid chemistry and voltage.

5. M O Loads such as selsmic, wind, thermal and dynamic.

6. 5 O Environmental conditions anticipated during storage, construc,lon and cperation such as pressure, temperature, humidity, corrosiveness, site elevation, wind direction, nuclear radiation, electromagnetic radiation and duration of exposure.10CFR50.49 applicability -

For electrical equipment only, reference above Safety Listing page er attach copy of Environmental Qualification Requirements form.

7. Gi O interface requirements including definition of the functional and physicalinterfaces involving structures, systems and components.

, 8. 5 O Material requirements including such items as compatibility, electrical Insulation properties, protective coating and corroslon resistance.

9. O JS1 Mechanical requirements such as vibcation, stress, shock and reaction forces.

10. O 3 Structural requirements covering such items as equipment foundations and pipe supports.

11. O E Hydraulic requirements such as pump not positive suction heads (NPSH), allowable pressure drops, and allowable fluid velocities.

12. O  % Chemistry requirements such as provisions for sampling and limitations on water chemistry.

13. X O Electrical requirements such as source of power, voltage, raceway requirements, electrical Insulation and motor requirements.

14. O  % Layout and arrangement requirements, to include potential adverse affects of non.

seismically quallfled masonry walls.

15. % C Operational requirements under various conditions, such as plant startup, normal plant operation, plant shutdown, plant emergency operation, special or infrequent operation, and system abnormal or emergency operation.

16. X O Instrumentation and control requirements including Indicating instruments, controls and alarms required for operation, testing, and maintenance. Other reouirements such as the type of Instrument, Installed spares, range of measurement, and location of Indication should also be included.

17. 3d O Access and administrative control requirements for plant security.

18, 3 O Redundancy, diversity and separation regulrements of structures, systems and components.

19. 3 O Failure effects requirements of structures, systems and components, including a definition of those events and accidents which they must be designed to withstand.

20. X C Test requirements including in plant tests and the conditions under which they will be performed.

21. $ 0 Accessibility, maintenance, repair and inservice inspection requirements for the plant including the conditions under which these will be performed.

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DESIGN DATA SHEET 1 i m Crystal River Unit 3 J Power SHEET 2 OF 2 ae,waa =va,.in o4f8 E 9 07 - o ( /4/zs/84 PINNECT SYSitM PibJ S - 055 4. er MSh c SYSTEMS R van no APPLICABLE DESIGN INPUT REQUIREMENTS: (Continued)

22. O p!! Personnel requirements and limitations including the qualification and number of personnel available for plant operation, maintenance, testing and inspection and permissibiu personnel radiation exposures for specified areas and conditions.

23. O 2Q Transportability requirements such as size and shipping weight, limitations, l.C.C.

regulations.

24. C 3 Fire protection or resistance requirements:

a. Changes or additions /dcletion of fire detection / suppression systems or equlpment.

b. Changes or additions to the plant configuration that change the effectiveness of existing fire detection / suppression systems.

25. 5 O Handling, storage and shipping requirements.

26. O O. Other requirements to prevent undue risk to the health and safety of the public.

27. 5 O Materials, processes, parts and equiment suitable for application.

28. 2 C Safety requirements for preventing personnel injury including such items as radiation

. hazards, restricting the use of dangerous materials, escape provisions from enclosures, and grounding of electrical systems.

29. C 5. Addition or relocation of safe shutdown equipment, systems, components, or circuits that require compliance with the separation criteria stated in 10CFR50, Appendix R.

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1. The principal function of the DSS is to prevent an ATWS by tripping the reactor, diverse from the existing RPS, to prevent a potential for damaging overpressurization of the RCS, if, for any reason, the rods have failed to drop in response to RPS trip.

, The principal function of the AMSAC is to mitigate the effects of an ATWS by actuating EFW and tripping the turbine to prevent serious RCS overpressurization, maintain fuel integrity and meet 10CFR release requirements in the

. unlikely event of no rod drop from either RPS or DSS.

2.- _ Performance requirements for the DSS are that the system is energize to trip the power to the gate drivers for the CRD SCRs of the regulating anc auxiliary groups when reactor coolant pressure exceeds 2450 psig. The total input instrument string error requirements is that it shall not exceed 1%. The electronic delay should not add more than one second to the overall time required to actuate the final actuated device.

The undervoltage trip remains the safety related CRD trip licensing basis for reactor protection. The DSS function will be a backup to the undervoltage trip function.

Performance requirements for the AMSAC are that the system is energize to trip the turbine and initiate EFW on a 100%

loss of main feedwater. The electronic delay should not add more than one second to the overall time required to actuate the final actuated device.

3. The separation between the safety related systa=s and non-safety related will be designed to meet FPC requireme.its document CR-3-E247-A "Electrical Separation critoria for Control Bocrds, Equipment Cabinets and Relay Racks", IEEE 279-1971, and 10CFR50, Appendix R.

The equipment installed in safety related system will be environmentally qualified to IEEE 323-1974 requirements.

The seismic qualification will be as to not degrade the safety grada equipment and will be designed to meet IEEE 344-1975 and IEEE 323-1974.

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(x,s 'i g DESIGN INPUT RECORD

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3. Cont'd This modification affects both safety and non-safety i systems:

l System Classification l

EFIC Safety l Rom.ote Shutdown System Safety l Gamma Metrics Safety NNI Non-Safety  !

CRDCS Non-Safety l MCB TGR Non-Safety Sequence Event Recorder Non-Safety NRC requirement 10CTR50.62 states that all Bt.W plants must have a diverse scram system from sensor output to interruption of power to the control rods. The rule also states that each PWR must have equipment from sensor output to final actuation device to automatically initiate the emergency feedwater system and initiate a turbine trip under condition indicate a ATWS.

NRC Generic Letter 85-06 states the quality assurance guidance for the ATWS equipment that is not safety related.

4. Environment -

Florida Power Corporation's "Environmental and Seismic Qualification Program Manual" Zone 13 - Elev. 145' 0",

attached, specifies the environmental conditions at the SER, NNI, and MCS TGR locations. The environmental conditions are Temperature 80 F Radiation - 1 x 10 4 Rad - 40 year Total Integrated Dose 1

l I

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(V,,........ Crystal River Unit 3 sn t 3 of 7 I amenam = **=

,. 84-o6-o7-o1 A0 f/B' pn, e ynsJs - Dss t 6tws A< SMTEms

4. Cont'd Zone 43 -

Elev. 108' 0", attached, specifies the environmental condition at the RSAE and Zone 58 - Elev. 124' 0", attached, for CRD Cabinets, EFIC, and the GM. The Environmental conditions are the same for Zone 43 and 58 and are:

Temperature 80 F 1

Relative Humidity 60%

. Radiation -

1 x 10 4 Rad -

40 year Total Integrated Dose Voltace -

The DSS and AMSAC systems will be powered from existing power sources within the systems where the new equipment

, will be located.

5. Florida Power Corporations "Environmental and Seismic Qualification Program Manual" Table A and Figure 14, attached, specifies the seismic design basis for the RSAE  ;

equipment. Table A and Figure 15, attached, specify the  ;

seismic design basis for EFIC, and GM equipment. The equipment selected to provide isolation between safety and non-safety systems for implementation of the DSS and AMSAC l functions will be qualified by the vender to IEEE 344-1975. l Test reports and vendor certification will be obtained during equipment procurement to document equipment qualification.

Seismic qualification of RSAE, EFIC and GM cabinets reflecting the additional equipment required to impleuent DSS and AMSAC functions will be documented.

6. operational environmental conditions for the equipment are those identified in No. 4 above. Prior to installation DSG and AMSAC electrical modules should be stored in a location meeting the requirements of ANSI N45.2.2 Level, A. The remaining equipment maybe stored in Level B.

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7. The following is a list of r.he interfaces:

1. DSS h Ig Isolation Function RSAE Cabirats AaB lion-Nuclear Inst: mentation IE to E Provide isolated (InfI) Cabinets RC WR Pressure signals c

}CTI Cabinets Centrol Pcd Drive Centrol E to E Trip & Enable ,

Systa::t (CRDCS) DC Hold Supply Contacts  !

Cabinet A CMX:S DC Hold Sequence of Events E to E Test & Ccnfirm Supply Cabirat A Recorder (SER) Conta#4 CRDs CC Hold Supply Cabirst A

}afI Cabinets E to E w & Cenfirm 0:ntacts

2. AMSAC Ga:::ma Metrics (Gi) 10TI Cabir.ets . 1E to E Prwide isolated IL Channals A&B Reactor Power i Ic'tel signals l-ICTI Cabinets. u AC A&D E to 1Z E!"W Actuation Contacts

!ctI cabirata H3 Lt E to E Turbine Trip Palay Contacts terI cetrots Sui E to E we ans cnfirm Centacts

/2.&&/4

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DESIGN INPUT RECORD kv ,)smaridaM Crystal River Unit 3 sn t T 9  ?

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8. All equipment added for this modification shall be new and not previously used. Equipment that has been in storage since manufacture and has not been previously used is considered new.

13. Power for the DSS and AMSAC equipment will be obtained from power sources within the existing systems where the equipment will be mounted. Wire insulation for DSS and .

AMSAC equipment installation shall be of the same type as the system in which thei equipment is located. Cables used to interconnect the systems shall be safety grade from the CR-3 cable Bill of Material.

15. The AMSAC and DSS needs to be operational only during power operation and those conditions indicative of an ATWS which I are LMFW and LCCP. i

16. The DSS input parameter shall be RC Pressure, from the RSAI

. cabinets, ad changed will have a range of 0 to 3000 psig.

The AMSAC input parameters shall be main feedwater flow from j the 10iI system which has a range of 0 to 6 x 106 t/hr and reactor power from the Gamma Metrics system which has a range of 10~3 to 200% power.

Installed spares for the DSS and AMSAC systems are not required.

Analog indications of DSS and AMSAC system functions are not required. Analcq indications of DSS and AMSAC input parameters are already installed whera required.

Inputs are to be provided to the sequence events recorder to identify when the DSS or AMSAC systems have actuated or have been placed in test.

The DSS system is to provide trip of the reactor based upon high RC pressure. Modules and components to achieve this control action are to be mounted in the 10!I and CRD systems.

The RC pressure signal is to be derived from the RSAI cabinets.

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16. Cont'd The AMSAC system is to provide turbine trip and initiation i:

of EFW based upon total loss of main feedwater. The' modules p and components to achieve this control action are to be mounted in the NNI, MCS TGR, Gamma Metrics and EFIC systems. I The main feedwater flow signals are available in the NNI cabinets. Reactor power level will be obtained at the Gamma Metrics equipment.

Safety grade to non-safety grade isolation is provided between safety and non-safety systems.

17. Existing administrative controls are arsquate.

18. Redundancy - Two channel system for both DSS and AMSAC Separation and isolation will be required from the following

, .ufety related systemst 1) RSAE A&B, 2) EFIC A&D, 3) GM A&B.

19. CRDMS must deenergize on Loss of Offsite Power (LOOP) so as to have an energize-to-trip DSS.

AMSAC must initiate on a LOOP.

20. DSS -

Upon completion of installation of the DSS, testing is tn be performed to independently verify operation of the total

i. } circuitry used to trip the CRD gate drivers. After the l initial installation tasting the DSS shall be tested every 6 months and every refueling. Testing at any time does not include the input sensors or dropping of the control rods.

AMSAC -

Upon completion of installation of the AMSAC, testing is to be performed to independently verify operation of the total circuitry used to trip the turbine and initiate EFL After initial installation testing the AMSAC shall be tested every '

6 months and every refueling. Testing at any time does not include the input sensors or final actuation device.

)

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I"'N DESIZ)N INPUT RECORD Crystal Rivw Unit 3 )

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21. The safety related portions of the ATWS system, inputs from GM, RSAE and EFIC actuation, will continue to use the maintenance, repair, and inspection procedures tnat apply.

The maintenance, repair, and inspection procedures used for non-safety systems will be used for the non-safety DSS and AMSAC circuitry.

25. Electronic modules handling, storage, and shipping requirements will be in accordance with ANSI N45.2.2 Level A.

All other itens on the bill of material are to be handled, stored, and shipped in accordance with standard vendor /FPC methods for that type of material.

27. The electrical components. wire and cable required for this modification shall be new and suitable for use in the system and environment in which it is located. Equipment that has

, been in storage since manufacture and has not been previously used is considered new.

28. Normal plant procedures for fabrication, installation, checkout, and operation of equipment are to be followed.

29. The equipment added in the RSAE Cabinets will be in l

compliance with the separation criteria stated in 10CTR50, Appendix R.

1 I

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$ l YN h.f hb f b V

- , , , 913 843

FLORIDA POWER CORPORATION Crystal River Unit 3 13 ZONED i

r Zone Environmental Data Revision 2 OBSCRIPMQN: Date 10/85 Ele,.143' - Centrol Couples, Bemen Mme M ad W Parameters Normai Enwronment trmronment For Loss trmrorwnent for High Energy Temperature Of Coolant Acedent Une treak (Inside As a is) l' '

th1MDCAAC IRES. 321

(*F)

It018. 3 011 12218.

s760 ro to ao N/A N/A Pressure (PSIG) AtmosphenC EC,1 Pft1L P

Ett Util

> N/A, N/A ..

• i

) Relative 40 to 40 N/A HumiditW%) M** 5. ,

! N/A 1

'# 'Y

( N/A N/A N/A l

Radiation (Rads) 40YeaeOose Mme Post

! Ag ggig 1.0 a 104 1 Er N/A l' N/A 1 Day N/A i

> 3 Days N/A

30 Days N/A

4 Nonths N/A 1 40 Tr. Total + 6 Mo. =

I 1.0 a 104 Total Submergence yfg yfg i (Flood Leve4) gfg i i I 1

l I [

l LEGENO:

NOTES; N/A a Not Acclicacie.N/C a Not Calculated  !

i

,___._-- - - ._ _ _ _ _ _ _ _ _ _ L.

Pl.ORIDA POWER CORPORAT13N Crystti River Unit 3 ZONEo 43 Zone Environmental Data Revision i I

j DESCRIPTION: gtey, Date uns 95' and 108' . control complex Parameters Normal Environment Environment For t.oss Environment for High Energy Of Coolant Accident Une Break (Inside A8 4181 romperature souruvear h rim, h nme m M 4760 70 to 80 N/A N/A s

Pressure (P51G) Atmosphenc Ume Pftg3L Mme P;31L '

N/A N/A .

Relative Humidity (%)

40 tc. 60 N/A *' A N/A Chemical Soray ,

(pH) M/A N/A N/A Radiation (Rads) 40 Year Dose Time Post Accident Q21g 1.0 x 10' 1 Mr Note 1 N/A i Day Note 1 3 Days Note 1 30 Days Note t 6 Months Note 1 '

40 Tr. Total + 6 Mo. =

1.0 x 10' Total Submitrgence (Flood Levei) Nld N/A N/A LEGEND: N/A s Not Acclicacle, N/C a Not CalcJtated NOTES: (1);otal 6 Moeth Integrated Accident Dose f,100 Rads.

FLORIDA POWER CORPORATION Crystal RivCr Unit 3 ZONEO sa Zone Environmentai Data Revisio n ,. t I

Date 4/s3 OESCRIPTION: Elev. 124' & 134' - Control Complex Pararneters Normal Environment Environment For Loss Environment for Nigh Energy

- Of Coolant Accident Une Break (Inside As a it)

Temperature Mours/ Year Um' It".UA. It!!1 h h

(*F) 8760 70 to 80 N/A N/A 1 e 1

, Pressure (PSIG) Atmosphenc Um* .PI21L Um' PI.111.

N/A N/A ,

Relative 40 to 60 U*'

Humidity (%)

N/A 1 g7g Chemical Spray -

(pH) N/A N/A N/A Radiation (Rads) 40 Year Oose Time Post Accident 2211 1.0 x 10' 1 Er N/A N/A 1 Day N/A 5 Days N/A 30 Days N/A 6 h aths N/A 40 Tr. Total + 6 M. =

1.0 x 10' Total Submergence (Flood Levei) N/A N/A N/A LEGENO: N/A e Not ApplicaDie, N/C a NotCalculated NOTES:

FLORIDA POWER CORPORATIOW I b CRYSTAL RIVER UNIT 3

[; / i TA31,E A PANEL /CASINET NOUNTED EQUIPMENT CloUwD az$rovst SPECTRUM FACTORS Buildina Elevation Demoint (%) _ CBS Factor (I)

Reactor Building Shell 106.00 1/2 10.8 Beactor Building Shell 123.00 1/2 21.0 Reactor Building Shell 139.00 1/2 33.0 Reactor Building Shell 154.00 1/2 45.0 i Reactor Building Shell 207.00 1/2 84.0 Reactor Building Interior 118.00 1/2 17.7 teactor Building Interior 123.00 1/2 20.7 Reactor Building Interior 135.00 1/2 29.7 teactor Building Interior 160.00 1/2 49.2 teactor Building Interior 180.50 1/2 60.0 Auxiliary Building 119.00 1/2 16.2 Auxiliary Building 143.00 1/2 27.0

. Auxiliary Building 162.00 1/2 31.2 Control Building 108.00 1/2 8.1 Control Buildir.g 124.00 1/2 12.0 I control Building 134.00 1/2 15.9 Control Building 145.00 1/2 20.4 control Building 163.83 1/2 28.4 control Building 183.83 1/2 35.9 Intermediate Building 149.00 1/2 21.8 Diesel Generator Building 143.00 1/2 21.0 Cround Response, Base Mac Reactor, Auxiliary, Intermediate, Control, and Diesel Generator Buildings varies 1/2 5.7 Auxiliary Building 193.58 1/2 101.0 Auxiliary Building 209.08 1/2 131.0 Emergency Feedvater Tank Facility 118.5 1 20.1 F.mergency Feedwater Tank Facility 143.0 1 72.0 Emergency Feedvater Tank Facility 168.0 1 115.0 Notest (1) The Required horizontal OBE Response Spectrum (RRS) to be used for qualification of panet/ cabinet sounted devices is obtained by multiplying the Regulatory Guide 1.60 Cround Response Spectrum (ORS), Figure 24, by ,

the above factor associated with the appropriate building and elevation where the equipment is located.

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FRE4UENCY ACCELERATIS06 FSE4WENCY ACCEtERATItet FRE4GENCY ACCELER4IItet FRE49680CY ACCELERAllett 8.500 0.048 e.600 e.848 8.700 0.444 8.844 8.488 '

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1.300 8.200 1.408 8.200 1.500 8.204 1.444 0.264 0.288 1.948 S.200 0.204 1.788 0.200 1.888 2.444 2.180 0.248 2.200 0.200 2.300 0.204 2.446 8.200 2.500 0.200 2.648 8.200 2.784 0.202 2.848 6.243 2.900 0.285 3.888 0.264 3.154 8.209 3.340 8.218 3.458 8.218 3.600 8.228 3.800 8.235 4.846 8.244 4.288 4.25e 4.40s 8.255 4.648 4.264 4.884 6.265 5.000 8.267 5.250 0.278 5.588 8.27f 5.754 8.267 6.000 8.2&& 6.258 a.268 6.584 0.254 4.758 4.248 7.000 0.238 7.258 8.228 7.500 e.225 7.758 e.204 S.See e.Its S. Set 8.175 9.See 4.158 9.544 8.145 14.000 0.144 10.544 4.140 11.000 0.144 11.544 e.144 12.400 0.147 12.500 e.858 13.888 0.868 11.500 e.164 ,

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17.008 8.213 18.084 0.218 28.000 0.228 22.884 0.238 25.888 0.190 28.084 e.383 31.008 8.384 34.440 0.181 34.888 8.185 40.000 8.las 45.888 0.148 54.888 4.144 i

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FREtuENCY ACCELERAllett FRET #ENCY ACCELERAlleN FREGUENCY ACCELERAlleet FREtteE80CY ACCELERAIIt00 e.See 0.84e e.600 0.e44 e.700 e.864 e.444 e.ess s.9ee e.114 1.ee8 4.154 1.las 4.17e 1.2ee e.lat 1.34e 4.182 1.400 0.167 1.588 4.148 1.4e8 0.844 1.78e 0.158 1.488 e.15e 1.988 6.148 2.000 e.147 2.les 3.148 2.20e 0.148 2.384 0.149 2.448 0.15e 7.588 0.152 2.668 4.153 2.700 e.354 2.848 0.154 l 2.988 S.155 3.888 8.142 3.158 0.163 3.364 0.172 l 3.458 S.18e 3.600 e.198 3.800 0.214 4.884 0.220 ,

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S SAFETY CLASSIFICATION REVIEW Crystal River Unit 3 nem cemeeneae

. A-Tus- Oss i Ptms At sysTE m s ,_

Generic 0 Yes G No Application

~ *

"sed.E" mes na e o. me was see.

R. G.

s.r.ty n.iei.o a Yes O No O Yes Does the itenvoeMee aneure the integrity of the reactor coolant system boundary (i.e.,"Pressure-retaining"as dennedin ASME Sodef and Pressure Vessel Code)?

2 Not part of reactor coolant system, a Not pressure-retaining per Code.

,El No

. 2 Yes Does the item /seMce assure the caoatality to shut down the reactor and to maintain it in a saf e snut.

down condition?

(11 no, justification is on attacntnenth C No O Yes Does tne item /semco assure tne cacaouity to pre.

vent or m6tigate the consequences of acc6 dents which could result in potential of f site es posures compareede to incee ref erred to in 10CFR100.117 (If no, justification is on attachment)

C No item /$ervice le Safety Aeleted item /SeMee is Non Safety.

Related NOTE:

If item la cons 6dered to be electncal equipment, the Environmental Quellficetion Requiremente Rev6ew form must be cornpleted to detemine 10CFRSO.49 sopl6cao4tity.

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N - o 6 -o i-o ( /o/2 s/e4 project b'{lds- 055 t %^s % aYS W 5 Does the item / service assure the capability to shut down the reactor and to maintain it in a safe shutdown condition?

, No, the DSS does shut down the reactor but it is only a backup function to the safety related Reactor Protection System trip.

The DSS or AMSAC does not maintain the reactor in a safe shutdown condition. The non-safety status of the ATWS system, DSS and AMSAC, is in accordance with the NRC Generic Letter 85-06.

Does the item / service assume the capabil ity to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to those referred to in 10CFR100.117 Yes, of the ATWS system, the DSS does prevent consequences of an ATWS and the AMSAC system does mitigate consequences of a ATWS to within the limits of 10CTR100.11. The non-safety portion of ATWS systems is in accordance with the NRC Generic Letter 85-06. The safety related and non-safety system except for the CRD breakers are assumed to function properly during an ATWS event.

The DSS and AMSAC systems are not required to be safety related.

However, these systems interface with EFIC, RSAE Cabinets and the Gamma Metrics equipnent which are classified as safety related.

The DSS t.nd AMSAC interfaces with these systems are therefore safety related. All other parts of this modification are non-safety related.

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1. Does the design / design change involve the modificaiton, addition, removal, or relocation of any of the following? If yes, explain in space provided.

.C C a. Combustibles (oil, hydraulic fluid, grease, wood-based materials, cloth, charcoal, PVC, cable insulation, carpet, etc.)

, See r %'e c utoe-h'e_s 4 p( Ch en bleI w1 W thMIa b e.,tl\ W ,num mJerl AoAm el- W el cl a s. h O Ci b. Available Fire Protection (detectors, fire extingulhers, hose stations, sprinkfors, halon system, CO2 system, etc.)

O d!I c. Equipment, components, or cables that would interfere with the operation of existing fire detection, emergency lighting, or other fire protection features.

C )if d. Penetrations, penetration seals, or conduit seals.

M C1 e. Space Separators (walls, ceilings, floors, doors, curbs, dampers, etc.)

4tl.19e <oed( h+ mhe b u Mrd a t k- uM {\ k u A J ~ Lues. L. A- MI A co n

)0 C f. Fireproofing, exposure fire protecttbn, cable tray covers / wrapping, conduit wrapping, etc.

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2. C di Will this design / design change require 9 revision to the Fire Hazards Analysis? Reference EG-4, Sect. V.O.

3. O JE Does this design / design change deviate from any applicable NFPA Fire Code requirement in safety related or safe shutdown areas / zone? if yes, explain below and obtain Fire Protection Engineer review and concurrence, essc= a=oast. s4te e,as *=orectio., a=ome sa c, .-. ., a o4:e EY$8

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I TEST OUTLINE Diverse Scram System (DSS) ,.

NNI-X (NNI-Y Similar)

1. Place test switch in enable.

2. "Enable" light lit.

3. "Trip 1 Enable" light lit. (NNI-X & Y)

' 4. DSS in Test - SER on.

5. Place test switch in test.

6. Adjust voltage source above setpoint to trip bistable.

7. '"CRD~ Actuate" light lit.

, 8. "Trip 1 Confirm" light lit.

9. DSS Trip 1 - SER on.

10. Place test switch in enable.

11. "Trip 1 Confirm" light of f.

12. DSS Trip 1 - SER off. I

13. "Enable" light lit.

14. "Trip 1 Enable" light lit. (NNI-X & Y) i

15. Place test switch in off.  ;

16. DSS in Test - SER off.

17. All lights off.

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_f CRD Test and Seal-in Circuit

1. "Trip 1 Armed" light lit.

2. "Trip 2 Armed" light lit.

3. Place 31-1 in enable.

4. "Test 1 Enable / Bypass" light lit.

5. "Trip 2 Armed" light off.

6. DSS in Test - SER on.

7. Place Sl-1 in test.

8. "Trip 1 Confirm" light lit.

'9. DSS Trip 1 - SER on.

10. Place Sl-2 in enable.

11. "Trip 1 Confirm" light of f.

12. DSS Trip 1 - SER off.

13. "Test 2 Enable / Bypass" light lit.

14. "Trip 1 Armed" light off.

15. Place Sl-2 in test.

16. "Trip Lockup" light lit.

17. Place Sl-2 in off.

18. "Trip 1 Armed" light lit.

19. "Test 2 Enable / Bypass" light off.

20. "Trip 1 Confirm" light lit.

21. DSS Trip 1 - SER on.

22. Reset S2

23. "Trip Locxup" light off.

24. Place S1-2 in test.

25. "Test 2 Enable / Bypass" light lit.

26. "Trip 1 Armed" light off.

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27. "Trip 1 Confirm" light of f.

28. DSS Trip 1 - SER off.

29. "Trip Lockup" light on.

30. Place Sl-1 in off.

31. "Trip 2 Armed" light lit.

32. "Test 1 Enable / Bypass" light of f.

e 33. "Trip 2 Confirm" light lit.

34. DSS Trip 2 - SER on.

35. Reset S1

36. "Trip Lockup" light off.

37. "Trip 2 Confirm" light lit.

38. Place Sl-2 in off.

. 39. "Trip 2 Confirm" light off.

40. "Trip 1 Armed" light lit.

41. DSS Trip 2 - SER off.

42. DSS in Test - SER off.

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ATWS Nitigation System Actuation Circuit (AMSAC) '

a NNI-X (NNI-Y Similar) ,

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1. Place test switch in enable.  ;

2. "Enable" light lit. l p 3. AMSAC in Test - SER on.

4. Place test switch in test. [

. 5. Adjust voltage source of flux bistable above setpoint.

6. Adjust voltage source of loop A main feedwater flow signal :

above setpoint.  !

7. "Trip" light lit.

8. "Turb Trip Conf" light lit.

9. AMSAC Trip - SF.R on.

10. EFIC A EFW Tripped - on EFIC panel.

11. Place NNI-Y test switch in enable.

12. "Turb Trip Conf" light off.

13. Place NNI-Y test switch in off.

14. "Turb Trip Conf" light lit.

15. Adjust voltage source of flux bistable below setpoint.

16. "Trip" and "Turb Trip Conf" lights of f.

17. Adjust voltage source below setpoint of loop A main feedwater flow signal.

18. Roset EFIC A.

19. Repeat steps 6-13 for other voltage source for loop a main

. feedwater flow signal.

20. Place test switch in enable.

21. "Turb Trip Conf" light off.

22. Place test switch in off.

23. AMSAC in Test - SER off.

24. All lights off.

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