ML18018A385

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Informs That Topical Rept AAF-TR-7101, Design & Testing of Fan Cooler-Filter Sys for Nuclear Applications, Acceptable. Partial Equipment Qualification Data Packages Encl
ML18018A385
Person / Time
Site: Harris  Duke Energy icon.png
Issue date: 11/10/1972
From: Tedesco R
US ATOMIC ENERGY COMMISSION (AEC)
To: Fish J
AMERICAN AIR FILTER CO.
Shared Package
ML18018A382 List:
References
NUDOCS 8210260481
Download: ML18018A385 (62)


Text

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VNlTED STATES ATOMIC ENERGY COMMISSION

,WhSHINGTON, D.C tOSi$

NO'v Hr. James F

Fish, Manager Nuclear Environmental Systems, American Air Filter Company, Inc.

215 Central Avenue Louisville, Kentucky 40201 Dear Mr. Fish The Regulatory staff has completed its review of Topical Report AAF-TR-7101, "Design and Testing of Fan Cooler-FIlter Systems for Nuclear Applications," submitted with your letter to Dr. P. A; Morris, dated March 23, 1972, and Supplement 1

to this report, submitted with your letter to Mr. J.

P. O'eary, dated August 21, 1972.

This is to inform you that we find the information on the AAP supplied components as represented in the report AAF-TR-7101 to be acceptable, by reference, in applications for construction permits and operating licenses, provided that the information is demonstrated to be applicable to the referenced application.

A summary of our review is enclosed for your information.

Sincerely,

'%Few 8'l

~s'obert L. Tedesco, Assistant Director for Containment Safety Directorate of Licensing

Enclosure:

As stated 82i026048l 822 020 PDR ADOCN 05000400 PDR

P

Response

480.34 (Clarification)

Attached are relevant portions of WCAP 8587 which was referenced in the original CP&L response.

0480.34-2 WESTINGHOUSE CLASS 3 WCAP-8587 Supplement 1

Revised November 1978 APPROVED:~ T. M." Anderson, Manager Nuclear Safety Department

$480.34-3 TABLE OF CONTENTS Section 1.0 2.0 3.0 4.0 5.0 Title

. Purpose Scope Performance Specifications Correlation to IEEE Std 323-1974 Interface Requirements EQUIPMENT QUALIFICATION DATA 'PACKAGES {EQDP)

TAB 1

EQDP-HE-1 EQDP-HE-2 EQDP-HE-3 EQDP-HEM EQDP-HE-5 EQDP-HE-6 Safety Related Valve'Electric Motor Operators:

Qualification Group A

~ H Safety Related Solenoid Valves:

Qualification Group A Safety Related Externally Mounted Limited Switches:

Qualification Group A Safety Related Valve Electric Motor Operators:

Qualification Group B

Safety Related Solenoid Valves:

Qualification Group B

Safety Related Externally Mounted Limit Switch s:

Qualification Group B

TAB 2 EQDP-ESE-1 Pressure Transmitters:

Qualification Group A EQDP-ESE-2 Pressu:e Transmitters:

Qualification. Group B

EQDP-ESE-3 Differential Pressure Transmitters:

Qualification Group A EQDP-ESE-4 Differential Pressure Transmitters:

Qualification Group B

EQDP-ESE-5 EQDP-ESE-6 EQDP-ESE-7 Resistance Temperature Detectors:

BC Bypass Manifold Resistance Temperature Detectors:

Mell Mounted

\\

Resistance Temperature Detectors:

Fast

Response

EQDP-ESE-8 2 Section, Excore Neutron Detectors:

Power Range EQDP-ESE-9 Excore Neutron Detectors:

Source E Intermediate EQDP-ESE-10 Nuclear Instrumentation System (NIS)

EQDP-ESE-ll NIS - Source Range Preamplifier:

(Out of Containment)

Q480e34-4 Section EQDP-ESE-12 EQDP-ESE-13 EQDP-ESE-14 Title Main Control Board Switch Modules Process Protection System r

Indicators, Post-Accident Monitoring EQDP-ESE-15 Recorders, Post-Accident Monitoring EQDP-ESE-16 EQDP-ESE-17 EQDP-ESE-18 EQDP<<ESE-19 Solid-State Protection System 8 Safeguard Test Cabinet (2 Train) r

'1 Solid-State Protection System 5 Safeguard Test Cabinet (3 Train)

Instrument Bus Power Supply (Static Inverter) -7.5 KYA Instrument Bus Distribution Panel -7.5 KVA EQDP-ESE-20 Reactor Trip Switchgear DS-416 EQDP-ESE-21 Pressure Sensor

.EQDP-ESE-22 4 Section Excore Neutron Detector EQDP-ESE-23.

Loop Stop Valve Cabinet EQDP-ESE-24 RCP Speed Sensor EQDP-ESE-25 Main Control Board, Primary Control Console, Secondary Control

Console, Safety Center EQDP-ESE-26 Reactor Trip Switchgear - DS206 EQDP-ESE-27 Nitrogen-16 Detector EQDP-ESE-28 Rod Position Detector EQDP-ESE-29 Rod Position Data Cabinet EQDP-ESE-30 Integrated Protection Cabinet EQDP-ESE-31 Integrated Logic Cabinet EQDP-ESE-32 Field Termination Cabinet EQDP-ESE-33 Instrument Bus Distribution Panel - 15 KVA

Q480.34-5 1.0

~Poc oee WCAP-8587 describes the methodology that Westinghouse PMRSD has adopted to qualify equipment to IEEE-323-1974, "IEEE Standard for Qualifying Class lE Equipment for Nuclear Power Generating Stations."

The purpose of this supplement is to demonstrate how the methodology described in MCAP-8587 is employed in establishing detailed performance requirements and consequent qualification program plans for. individual items of safety related electrical equipment suppl'.e~

by Westinghouse PWRSD.

~H This Supplement has been revised to specifically provide the information requested by the NRC via PSB draft Standard Question No. 4 'Environmental Qualification of Class lE Equipment'nd to include Equipment Qualification Data Packages for the safety related electrical equipment in the Mesting-house NSSS scope of supply for all reactor models, including the RESAR-414 standard application, coraoitted to qualifying to IEEE-323-74.

2.0

~Sco e

Table 1 identifies the safety r lated electrical equipment currently within the Mestinghouse PWRSD scope of supply.

A separate Equipment Qualification Data Package (EQDP) is provided for each identified item of equipment.

These EQDP's currently specify the equipment performance requirements (Section

1) and qualification program plans to be employed, whether by test (Section 2), experience (Section 3),

by analysis (Section 4) or by some combination of these methods..

Q480.24-6 0

3.0 Performance S ecifications In order to provide the information requested by PSB draft Standard I

guestion No. 4, Section 1 of the EgDP's has been expanded to identify detailed functional requirements and associated environmental parameters In order to establish the appropriate enviqonmental parameters, assumptions have been made concerning the in-plant location of the equipment; Since equipment location is normally the responsibility of the Owner/AE,

~8 the environmental conditions have been conservatively derived to allow for possible'alternative locations of equipment within the plant.

The environmental parameters have been established employing the methodology presented in WCAP-8587, subject to the follow'ng:

3.1 Normal and Abnormal 0.itin Environments The plant location code, indicated in Table 1 for each

EgDP, has been used in conjunction with the environmental parameters presented in WCAP-8587, summarized for convenience in Table 2, to definp the applicable normal and abnormal environmental conditions provided in Section 1.8 of the EgDP's.

3.2 Accident Environments The accident environments specified in Section 1.8 of the EgDP's'ave been selected by Westinghouse for generic qualification to envelope the anticipated range of accident environments generated by plant specific analysis employing currently accepted calculational techniques.

QI480. 34-?

3.3 Radiation Ooses The total inte'grated dose to be specified for equipment qualification is a combination of:

a.

the dose incurred during the. life of the equipment in the radiation field at the equipment location appropriate to normal reactor operation.

b.

the dose incurred post accident at the ~quipment location

~r during the period the equipment is required to perform a safety related function.

The normal operating doses specified in Section 1.8 of the E(OP's are derived from the dose rates established in )~CAP-8587, summarized for convenience

'.n Tables 3 and 4 for inside and outside containment locations.

The accident doses specified in Section 1.8 of the E(OP s have been derived based on the time required to perform a safety function in the accident environment (ESTOP Section 1.7) and the post accident doses derived in WCAP-8587, reproduced here s Figures 1 - 5.

In the general area between the loop compartment wall and containment

annulus, the shielding affords a factor of approximately 2.7 reduction in the unshielded accident garana dose levels (ESTOP-ESE-1 thru 4 and 21).

$480. 3'4-8 For equipment located outside containment, the equipment is assumed P

to be isolated from the accident environment unless liable to experience a hostile environment resulting from a steam line or r

feedline break outside containment.

In which case the doses are allocated assuming an.in-containment location.

iii Certain pumps and.valves outside containment are utilized to recirculate, sump water post accident.

Accident doses for associated motors have

~r been derived from Figure 5 assuming a factor of 5 reduction in unshiklded gama dose level at the pipe center, to account for a motor located out-side the pipe boundary.

iv For equipment only required to function at ter accidents involving no release of radioactive material (i.e. loss of flow), the radiation dose is based on the normal. dose rates identified in Tables 3 and 4.

4.0 Correlation to IEEE Standard 323-1974 Mestinghouse developed the Equipment gualification Data Package (EQDP) format in order to comply with Section 8 of IEEE-323-1974.

Table 5 illustrates Mestinghouse's compliance'ith this standard by providing a comparison between sections of the EgDP and IEEE-323-1974.

5.0 Interface Re uirements Section 1, Performance Specifications, of the EqDP's establishes the functional requirements and associated environmental conditions against which qualification will be demonstrated.

This section acts as interface

Q480. 34-9 information to the User of Mestinghouse PMRSD supplied Class lE equipment.

The equipment shall be located and operated to ensure that the specification of Section

.1 is not exceeded.

Q480.34-10 TABLE 1 SAFETY RELATED EQUIPMENT IN M PMR-SD SCOPE OF SUPPLY (TYPICAL)

~Eui ment Pl ant Location++*

~Setem I.C.

O.C.

E DP Reference Safety Related Valve Electric Motor Operators Safety Related Solenoid Valve Safety Related Externa'ily Mounted Limit Switches Pressure Transmitters Differential Pressure Transmitters Resistance Temperature Detectors Excore Neutron Detectors Nuclear Instrumentation System (NIS)

Source Range Preamplifier Main Control Board Switch Modules Process Protection Sets Indicators and Recorders**

CVCS 0

SIS, 0

CSS RHR 0

CVCS

, 0 SIS 0

RCS*

0 MPS*

SS*

0 SGBP*

RHR 0

CVCS 0

SIS 0

CSS RHR 0

RCS*

0 MPS*

SS*

0

<GBP*

RPS/PAM 0

RPS/PAM 0

RPS/PAM I

RPS I

RPS RPS 0

RPS/ESF RPS PAM NV NV NV NV NV NY NV NY NV NV NY NV NV NV NV NV NV NV NV NY NV A.C.

A.C.

A.C.

A.C.

HE-1 and 4 HE-2 and 5

HE-3 and 6

ESE-1 and 2

'SE-3 and 4 ESE-5, 6,

and 7

ESE-8 and 9

ESE-10.

ESE-ll and 36 ESE-12 ESE-13 ESE-14 and 15

Q480.34-11 TABLE 1 (Continued)

SAFETY RELATED EQUIPMENT IN W PHR-SD SCOPE OF SUPPLY (TYPICAL)

~Eni ment Plant Location*~

~Sstem I.C:

O.C.

E DP Reference I

Solid State Protection System Logic and actuation Trains - (Auxiliary Safeguards cabinets (where applied) and, ESF on-Line Test Cabinet Instrument Power Supply (Static Invertor)

Instrument Bus Distribution Panel Reactor Trip Switchgear Pressure Sensor 4-Section Excore Neutron Detector Loop Stop Valve Cabinet RCP Speed Sensor Main Control Board Primary Control Console Secondary Control Console Safety Center Nitrogen-16 Detector Rod Position Detector Rod Position Data Cabinet Integrated Protection Cabinet Integrated Logic Cabinet Field Termination Cabinet PAMS Demultiplexer Control Board Multiplexer Fiber Optic Cable Hydrogen Recombiner RPS/ESF El ec-trical Power Supply Elec-trical Power Supply RPS RPS RPS RPS RPS RPS/ESF/

PAM RPS RPS RPS RPS RPS RPS RPS/ESF RPS/ESF ESF O

m A.C.

V '"

A.C.

A.C.

A.C.

A.C.

V/NV A.C.

A.C.

A.C.

ESE-16 and 17 ESE-18 and 25 ESE-19, 33 and 34 ESE-20 and 26 ESE-21 ESE-22 ESE-23 ESE-24 ESE-25 ESE-27 ESE-28 ESE-29 ESE-30 ESE-31 ESE-32 ESE-37 ESE-38 ESE-39 SP-1

Q480e34-12 TABLE 1 (Continued)

SAFETY RELATED EQUIPMENT IN W PWR-SD SCOPE OF SUPPLY (TYPICAL)

EcCEui ment Plant Location*~

~Sstem I.C.

O.C.

E OP Reference Safety Related Pump Motors CVCS SIS SFPCS EBS 0

AE-1 through 4

Notes:

I.C.

=

Inside Containment O.C.

=

Outside Containment I = Inside Secondary Shield 0

Outside Secondary Shield A.C. = Air Conditioned Area V = Ventilated Area NV = Non Ventilated Area Containment Isolation Val ves only Recorders must be in operation after seismic event; no requirements during seismic event.

For the Equipment listed below, the Applicant will be responsible for locating this 'equipment in a plant area which has environmental conditions within the equipment's normal, abnorrzl, and acc'dent environments (specified in each EODP).

CVCS = Chemical Volume Control System SIS

= Safety In'ection System WPS

= Waste Processing System SGBP - Steam Generator Blowdohn (Waste)

Processing (System)

RHR

= Residual Heat Removal (System)

PAM

= Post Accident Monitoring RPS

= Reactor Protection System ESF

= Engineered Safeguard Feature N/A

= Not Applicable SFPCS

= Spent Fuel Pit Cooligg System RCS

= Reactor Coolant System SS

= Sampling System CSS

= Containment Spray System EBS

= Emergency Bbration System

TASLE 2 Normal and Abnormal Operating Envfronments General Area Zone Zone Oescriptfon Code Typical Areas Normal Operation Temp RH Press.

Range

('F)

(5)

(psig)

Abnormal Operation Time Temp RH Press.

Limit

{'F)

(X)

{psig)

In-Containment Inaccessible IC/I Accessible IC/0 Inside Sec.

Hax Shield Hin Outside Sec.

Max Shield Min 135 7D

+0.3 65 20

-0 1

120 70

+D.3 65 20

-0.1 120 50 95 Atmos 0

Atmos 8 hrs 150 95 Atmos 50 0

Atmos

~ ~

Out of Contain-Air-Condi-OC/AC ment tfoned (a)

Ventilated OC/V Non-Yentf1-OC/NV ated Control room, Max Aux Equipment Hin Room 80 50 Atmos 60 30 Atmos Aux building Hax 104 70 Atmos Safeguards Min 60 20 Atmos etc.

Turbine-Hall Hax 104 70 Atmos Hin 60 20 Atmos 82 12 hrs 120 4D 82 12 hrs 120 40 82 120 40

~ 95 35 D

95 35 0

95 35 0

Atmos Atmos Atmos-Atmos Atmos Atmos AD 00 C7 l

lA Note a:

Abnormal operating parameters are not applicable for applfcatfons where Class lE air conditioning systems are supplied.

9480.34-14 TABLE 3 40 Year Normal Operating Doses - Inside Containment Location Y Dose rate R/hr 40 r dose R

RCL pipe center RCL pipe ID RCL pipe OD (contact)

RCL - general area Outside loop compartment wall Detectors located next to RV 820 470 165 50

<0.1 5xl0 3.0x10 1.6x10 5.8xl0'2.0x10

'3.5x10 1.8xl 0

$480.34-15 TABLE 4 40 Year Normal Operating Doses - Outside Containment Location 40 r

dose R

Penetration Area

<lx10 Pump Cubicles Radioactive Waste Area Radwaste Tank Cubicles Other general areas

<1 xl0

<4x10

0 Q480.34-16 0,

EQDP+E -1 Rev 1 ll/78 E UIPMENT UALIFICATION DATA PACKAGE This document contains information, relative to the qualification of the equipment identi-'ied below, in accordance with the methodology of WCAP 8587.

The Specification section (Part 1) defines the. assumed limits for the equipment qualification and consti tute interface require-ments,to the user.

SAFETY RELATED VALVE ELECTRIC MOTOR OPERATORS (guali fication Group A)

WESTINGHOUSE ELECTRIC CORPORATION NUCLEAR ENERGY SYSTEMS P.O.

Box 355 PITTSBURGH, PENNSYLVANIA 15230 Page I of 13

Q480.34-17 EQDP-HE -

1 Rev l. 11/78 EQUIPMENT 'ALIFICATIONDATA PART 1 - SPECIFICATIONS 1.0 PERFORMANCE SPECIFICATIONS 1.1 Electrical Requirements 1.1.1 Voltage motors in ran e 350-600 VAC 3 Phase 1.1.2 Frequency

+

1.1.3 Load As eci fied for each size of e".'gator

~ P 1.1.4 Electromagnetic Interference 1.1.5 Other N/A 1.2

. Installation Requirements The actuator shall be mounted on the valve as ma a

1. 3 Auxiliary Devices 1.3.1 1.3.2 1.3.3 A

or Voltage:

120 or 220 VAC nominal Frequency:

60 or 50 Hz nominal Load:

< 5 amp B

125 VOC nominal N/A

< 0.5 amp 1.4 Preventative Maintenance Schedule:

The details of an reventative mainten-ance schedule, assumed in establishin the ualified life will be s ecified in this sectior.

on corn letion of the ualification ro ram.

1.5 Design Life 40 ears 1.6 'perating Cycles 2000 for 40 ear life Page 2 of 13

e 1,7 Performance Requfrements for Function

( )( ): All safety-related functions E(DP-HE -1 Rev 1 11/78 Condition Parameter Normal Abnormal 1.7.1 Time requirement continuous included under normal Cont.

Test test duration FLB/SLB

< 8 hrs DBE LOCA

< 8 hrs SEISMIC event duration SEISMIC continuou Post OBE FLB/S1B 4 months LOCA 4 months 1.7.2 Per'formance requirement Note a no damage Note b Note b Note b as normal maintain position maintain position 1.8 Environmental Condition s for Same Function(4 1.8.1 1.8.2 1.8.3 Temperature (oF) 50 120 Pressure (psig) 0.1/+0.3 f{umfdity ('X RH) 0-95 c

U under normal ambient 70 ambfent Fig 2 Fig 2 100 Fig 1

Fig 1

100 ambient 0

ambient ambient cond)tion Fig 1

Fig 1

100 Fig 2 Fig 2 100 1.8.4 Radiation (R) 2xl0 y

7 Hone 2.2xlO y 4

lxl05g 1.5x107y 7

9.5xl0 g

None 1.1xl0 r 9xl08 8

1. Oxl 0555 6.4x10 B

1.8.5 1.8.6 1.8.7 Chemicals Vibration Acceleration (g)

None (later.)

None None None Hone Fig 2 None None Fig 1

None Hone None None 4/4/4 Fig 1

Hone None Fig 2 Hone Hone Note a:

Actuator to stroke with presp'ecified thrust and speed of operation established by supplier, Hote b:

As note a, except that supply voltage shall be ")l Page 3 of 13 of nom'

Q480.34-19 EQDP-HE -4

', Rev 1 ll/78 E UIPMENT UALIFICATION DATA PACKAGE This document contains information, relative to the quaIification of the equipment identi-fied below, in accordance with the methodology of MCAP 8587.

The Specification section (Part 1) defines the assumed limits for the e~uipment qualification and constitute interrace require-ments to the user.

SAFETY RELATED VALVE ELECTRIC MOTOR OPERATORS (Qua1ification Group B)

WESTINGHOUSE ELECTRIC CORPORATION NUCLEAR ENERGY SYSTEMS P.O.

Box 355 PITTSBURGH, PENNSYLVANIA 15230 page 1 of ll

9480.34-20 EQDP-HE-4 Rev l. ll/78 E UIPMENT

. UALIFICATION DATA PART 1 - SPECIFICATIONS 1.0 PERFORMANCE SPECIFICATIONS 1.1 Electri cal Requirements 1.1.1 1.1.2 1.1.3 Voltage motors in range 350-600 VAC, 3 Phase Frequency 60 or 50 Hz - 5X

+

Load As specified for each size of act".ator 1.1.4 Electromagnetic Interference 1.1. 5 Other N/A N/A 1.2 Installation Requirements The actuator shall be moun d o as specified by the actuator manufacturer.

1 3

Auxi]iary Devices~

~

Integral limit switches and tor ue switches or

1.3.1 Voltage

120 or 220 VAC nominal

1.3.2 Frequency

60 or 50 Hz nominal 1.3.3 Load:

<5amp 125 VOC nominal N/A

<0.5 amp 1.4 Preventative Maintenance Schedule:

The details of an reventative mainten-ance schedule, assumed in establishin tt o ual ified life will be s ecified in this section on corn letion of the ualificatjon ro ram.

1.5 Design Life 40 years 1.6 Operating C cles 2000 for 40 year lif Page 2 of 11

1.7 Performance Requirements for Function (")( ):

E(DP-HE - 4 Rev 1 ll/78 Condition Parameter Normal Abnormal Cont.

Test FLB/SLB DBf LOCA SEISHIC

>SEISMIC LOCA Post DBE FLB/SLB 1.7.1 1.7.2 Time requirement Perf ormance requirement continuous included under normal Note a

N/A event duration Note b event event duration duration Note b Note b continuou Note a

<<1 yr Note b

<<1 yr Note b 1.8 Environmental Condition s for Same Function("

t ~

1.8.1 1.8.2 1.8.3 Temperature (oF)

Pressure (psig)

Humidity (X RH)40-120 0

0-95 included under normal H/A ambient 0

ambient 0

ambient 0

-- ambient ambient ambient ambient conditio ambient 0

ambient ambient 0

ambient 1.8.4 R adi ation (R)

< 106 see post DBE see post DBE Hone

<4x106

<<4xl0 y

6 1.8.5 1.8.6 1.8.7 Chemi ca 1 s Vibration Acceleration (g)

Hone (later)

Hone None Hone None None None None None None 4/4/4 None Hone None Hone Hone None Note a:

Actuator to sn oke witn prespecH'ieJ thrust and speed of operation established by supplier Note b:

As note a, except that supply voltage shall be 80K of nominal.

note c:

poses apply to valves located in i)nes carrying radioactive fluid.

For other appli 'tions the nag.mal operatjxq dose is <4xl0.

and no additional dose is incurred due to.DBE Page 3 of ]I envi

.ents.

I gl

q480. 34-22 EgDP-ESE-1 Rev 1 ll/78 E UIPMENT UALIFICATION DATA PACKAGE!

This document contains information. relative to the qualification of the equipment identi-fied below, in accordance with the methodology of MCAP 8587.

The Specification section ('art 1) defines the assumed limits for the

=-equipment qualification and constitute interface require-ments to the user.

Pressure Transmitters - qualification Group A WESTINGHOUSE ELECTRIC CORPORATION NUCLEAR ENFRGY SYSTB5 P.O.

Box 355 PITTSBURGH, PENNSYLVANIA 15230

Q480. 34-23 EQDP-ESE-1 Rev l. 11/78 E UIPMENT UALIFICATION DATA PART 1 - SPECIFICATIONS 1.0 PERFORMANCE SPECIFICATIONS 1.1 Electrical Requirements yoltage 4O VDC + ly 1.1.2 Frequency N A

'.1.3 Load 4-20. RA 1.1.4 Electromagnetic 'Interference None 1.1.5 Other None 1.2 Installation Requirements Wall Mounted er Westin house drawin 1.3 Auxiliary Devices

~

None 1.4 Preventative Maintenance Sche'dule:

The details of an reventative mainten-ance schedule, assumed in establishin the ualified life, will be s ecified in this section on corn letion of the ualification ro ram.

1.5 Design Life '0 ears (2) 1.6 Operating Cycles Continuous Page 2 of U

~ ~

1.7 Performance Requirements for Function (4)(5):

Reactor Coolant System Pressure (MR).'(DP-ESE-1 Rev 1 11/78-Condition Parameter Normal Abnormal Cont.

Test DBE FLB/SLB LOCA SEISMIC (6)

Post DBE SEISMIC (6)

FLB/SLB LOCA 1.7.1 Time requirement Continuous Included under normal Test duration Event Event duration duration Event duration 4

months 4

months Continuous 1.7.2 Perf ormance a) requirement b)

+ 1.0X K4 sec.

No damage As post DBE As post Note C

+ 8$

TO secs

+BX..

TO secs

+ 1.0Ã 0.4 sec..0 al Condition

1. 8 Environment s for Same Function(4 1.8.1 1.8.2 1.8.3 1.8.4 Temperature (oF)

Pressure (psig)

Humidity (X RH)

Radiation (R) 50-120

-0.1/+0.3 0-95

<4x104 Included

. under normal 70 Fig.

2 Fig.

3 Ambient l00 100 None See post See post DBE DBE Ambient Fig.

2 Fig.

3 100 4

3.9xlO y 5

6.4x10 B

100 4.1xlO 7

9x10 B

Ambient Fig.

2 Fig.

3 Conditions Fig.

2 Fig.

3 Ambient condi tions 1.8.5 1.8.6 1.8.7 Chemi ca ls Vibration Acceleration (g)

None None None None None None None None None None Fig.

2 Fig.

3 Fig 2 None None Fig.

3 None None a)

Reference accuracy specified b)

Time response (c)

Continued operation required, no specified accuracy.

Page 3 of l7

1.7 Performance Requirements for Function (4)(5):

Pressurizer Pressure ESTOP-ESE-l Rev l ll/78 r

Condition Parameter Normal Abnormal Cont.

Test FLB/SLB OBE LOCA SEISMIC FLB/SLB LOCA Post OBE SEISMIC (6) 1.7.1 1.7.2 Time requirement Perf ormance a) requirement b)

Continuous

'ncluded under normal

+ lX 0.4 sec.

Test duration Ho damage

< 5 mins

+ 10K

)0.4 secs.

< 5 mins

+ 10$

0.4 secs.

Event duration

+ 11K

1. 8 Environment al Conditions for Same Function(4 1.8.1 Temperature (oF) 1.8.2 Pressure (psig) 1.8.3 Humidity (X RH) 50-120

-0.1/+0.3 0-95 Included under normal 70 Fig.

2 Ambient 100 Ambient Fig.

2 Fig.

3 Fig.

3 100 Ambient Ambient 1.8.4 Radiation (R)

< 4x10 None 4

< 10 5

<10 B

6

< 10 y 7

<10 B

None 1.8.5 Chemicals 1.8.6 Vibration 1.8.7 Acceleration (g)

None None None:

None None Hone Fig.

2 None Hone Fig.

3 None None None None Fig.

1 a)

Reference accuracy specified b)

Time response Page 4 of17

1. 7 Performance Requirements for Function (4)(5):

Steamline Pressure EqOP"ESE"l Rev 1 ll/78 Condition Parameter Normal Abnormal Cont.

Test FLB BE SLB Seismic FLB SLB Post DBE eismic (6) 1.7.1 Time requirement Continuous Included under normal Test

<5 mins duration

<5 mins

.Event duration 4

months 4

months Continuous 1.7.2 Performance (a) requirement (b)

+ 1.0X 5.4 sec.

No damage

+ 10$

0.4 sec

+ 104 0.4 sec

+ 11K

+ 11K TO secs

+ 115 TO secs

+ 1X 0.4 secs 1.8 Environmen al Conditions for Same Function (4) 1.8.1 1.8.2 1.8.3 Temperature (oF)

Pressure (psi9) 50-120

-0.1/+0.3 Humidity (X RH) 0-95 Included under normal 70 Fig.

2 Ambient 100 Ambient Fig.

2 Fig.

2 100 0

Ambient Fig.

2 Ambient Fig.

2 Fig.

2 100 Fig.

2 Fig.

2 100 Ambient Continuou 1.8.4 Radiation (R)

< 4x10 Hone

< 10 5

<10 B

4

< 10 y 5

<10 B

None 4

4 3.9x10 y

3.9xlO 5

5 6.4x10 B

6.4x10 B

1.8. 5 1.8.6 1.8.7 Chemicals Vibration None Hone Acceleration (g)

None None None None Fig.

2 None None Fig.

2 None None None None

~

Fig.

1 Fig.

2 None None Fig.

2 None None a)

Reference accuracy specified b)

Time response Page 5 of l7

9480. 34-27 EgDP-ESE-2 Rev 1 11]78 E UIPMENT VAI IFICATION DATA PACKAGE This document contains informatiqn. relative to the qualification of the equipment identi-fied below, in accordance with the methodology "

of WCAP 8587.

The Specification section (Part 1) defines the 'assumed limits for the

~quipment qualification and constitute interface r'equire-ments to the user.

Pressure Transmitters:

gualification Group B

WESTINGHOUSE ELECTRIC CORPORATION NUCLEAR ENERGY SYSTEMS P.O.

Box 355 PITTS8URGH, PEHNSYLYANIA 15230 Page 1 of 12

Q480.34-28

'QDP-ESE-2 Rev l. 11/78 E UIPMENT UALIFICATION DATA PART 1 - SPECIFICATIONS 1.0 PERFORMANCE SPECIFICATIONS 1.1 Electrical Requirements 1.1.1 Voltage 40 VDC + IV 1.1.2 Frequency N A 1.1. 3 Load

.:4.- 20ma 1.1.4 Electromagnetic Interference NIA 1.1-5 Other None 1.2 Installation Requirements Mall mounted zs er M drawin 8765D65 or 8765D66 1.3 Auxiliary Devices 1.4 Preventative Maintenance Schedule:

The details of an reventative mainten-ance schedule, assumed in establishin the ualified life will be s ecified in this section on corn letion of the ualification ro ram.

1.5 Design Life 4O years 1.6 Operating Cycles continuous page 2 of 12

1.7 Performance Requirements for Function (4)(5):

Turbine Impulse Chamber Pressure E(DP-ESE-2 Rev 1 ll/78 Condition Parameter Normal Abnormal Cont.

Test FLB/SLB OBE LOCA SEISMIC (6)

FLB/SLB Post DBE SEISMIC (6)

LOCA 1.7.1 Time requirement Continuous Included under normal N/A N/A H/A Event duration N/A N/A Continuous 1.7.2 Perf ormance (a) requirement (b) 1.8 Environment

+ 1.0X 0.4 secs al Condition s for Same Function(4 I

)

+ 11%

+ 1.0X 1.8.2 Pressure (psig) 1.8.3 Humidity (X RH) 1.8.4 Radiation (R) 0- 95

< 400 1.'8.1 Temperature (oF) 50 - 120 Included under normal ambient ambient None

ambient, ambient Hone 1.8.5 Chemicals 1.8.6 Vibration Hone Hone None None Hone None 1.8.7 Acceleration (g)

None Fig.

1 Hone a)

Ref erence accuracy specified b)

Time response Page 3 o~ 12

Response

480. 37 (Clarification)

The hydrogen purge'xhaust inboard containment isolation valve (2CM-B5-SA) is a normally closed valve.

This valve is airmpezated and does not have a

manual operator or a method to lock the valve controls.

The valve shall be

closed, and the control switch will be tagged in the closed position.

Administrative controls shall be provided to ensure that the valve remains closed during all normal modes of reactor operation and that the valve shall be used only post-LOCA.

If this valve could be locked inside containment, there would be no way to open it in the event of a LOCA, when it is required to be open.

The outboard valve is normally locked closed, and it shall have administrative controls to ensure that the valve remains locked in the closed position during all normal modes of reactor operation.

This valve shall be used only pose-LOCA.

Both of the above valves shall be verified 'closed at least every 31 days, via control switch position (inboard valve) and valve check (outboard valve).

RESPONSE 480.38 CONTAINMENT ISOLATION SYSTEM DATA PENETRATlON DATA PENETRATtOtt DETAlt.

VALVE DATA

~

VILVE POSITION

~4v NOTE r

A 00

~

'Il L

4Q ep.v3Ãa TV 3

INC ORC

~

llh 105 54 56 RADIATION HOtlITOR AND BYDROGEtl ANALYZER V300 V302 V304 V306 V348 A

10 B

10 A

10 A

10 A

10 CL SO h

RH SO h

RH SO h

RH SO h

RH SO h

RH 3

0 3

0 3

0 3

C I,~-

3 0

0 0

C 0

C C

0 C

C C

0 C

0 0

C NO YES YE NO YES YKS NO YKS YhS NO YES YES IIO YES YhS i I 5P VSOT wc sac j TY 105 54 h

56 RADIATION HOB ITOR AND BYDROCEN ANALYZER V301 V303 V305 V307 V349 A

10 8

10 A

10 A

10 A

10 CL CI.

CL SO A

RH SO A

RH SO A

RH SO h

RH SO h

RH 3

0 3

0 3

0 3

C 3

0 0

0 C

0 C

C 0

C C

C 0

C 0

0 C

NO YES YES NO YES YES ttO YKS YES NO YES YES NO YES

'YES IRC ONC SP.V30$

eP.V314 105 56 BYDROCKN ANALYZER V308 V314 8

10 8

10 CL CL 3

C C

0 C

C 0

C tkt YES

'YKS NO YES YES IRK 0RC oV Sp v3o5 ep.vBt9 105 54 A

56 IIO BYDROCEN ANALYZhk V309 V315 10 8

10 CL CL SO h

RH SO h

RH 3

C C

0 C

C 0

C ltO YES YES NO YES Yt S

Res onse 480.40 (Clarification)

The Containment Pre-Entry Purge 42 inch butterfly valves are normally closed valves.

These valves are air-operated, and do not have a manual operator or a method to lock the valve controls.

The"valves shall be closed; and the control switch shall be tagged. in the closed position.

Administrative controls shall be provided to ensure that the valves remain closed during reactor operation.

The.valves shall be verified to be in the closed position at least every 31 days,'ia control switch position. If the valves inside containment could be locked closed, someone would have to enter Containment prior to operation of the Containment Pre-Entry Purge system to open these valves.

Response

to:

Subcompartment Analysis (Clarification)

Attached are revised FSAR Tables 6.2.1-12, 15, and 16 which correct previous typographical errors.

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~ 01502

~ 01603

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~ 01901

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.02104

.02'203

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~ 87 553.90 553.93 553.96 554.00 554.03 554.07 554. 11 554.15 3344e20 554.24 3344

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.26501

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.33006

.33503

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