ML20062A789

Forwards Final Response to NRC 820325 Request for Info on Franklin Research Ctr Concern Re Equipment Qualification

ML20062A789
Person / Time
Site:	McGuire, Mcguire
Issue date:	07/28/1982
From:	Parker W DUKE POWER CO.
To:	Adensam E, Harold Denton Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM NUDOCS 8208040169
Download: ML20062A789 (44)

Text

c c-DUKE POWEH COMPANY Powzu Dust.pswo 422 Sourn Gnuncu Srazer, Crummortz, N. C. sea 4a WILLI AM O. PA R M E R, J R,

%Ce Passiocut Tt t ermon g:Anta 704 src. Paooverio-July 28, 1982 m-4% 3 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S.. Nuclear Regulatory Commission Washington, D. C. 20555 Attention:

Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: McGuire Nuclear Station Docket Nos. 50-369, 50-370

Dear Mr. Denton:

Attached is the final part of Duke Power Company's response to the NRC Staff's request for information dated !! arch 25, 1982 concerning Franklin Research Center's (FRC) of equipment qualification. By letters dated March 23, 1982 and June 22, 1982 the documents requested by Part A of FRC's request were pro-vided.

Attachment A through H contain our response to Part B of FRC's request. Correla-tion between the Part B requests and the attachments to this letter is as follows:

Part B Request Attachment B.l.a,'b - Equipment Installed before or A

after 1/1/81 B.l.c

- Correlation of Equipment Items with B

Specific Sections of NUREG-0737 Installed Rf1 Action Plan Equipment C

B.l.d SCEW Sheets (in accordance with NUREG-0588 format) and Applicable Notes h

Environmental Profiles and Service D

B.l.c Conditions t

Approximate Installation Dates of E

l B.1.f TMI Action Plan Items

- B.2

- Qualification Documents (Cables)

F,G,H l

Owners Group. Position N/A B.3 l-l c-hO l

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Mr. Harold R. Denton, Director July 28, 1982 Page 2 Please note that Attachments F, G, and H are proprietary documents and as previously requested should be retained and reviewed by the NRC Staff. Upon completion of NRC review it is requested that these documents be returned to Duke Power Company.

Please advise if there are questions regarding this matter.

Ver,truly yours, i

A.__.a.

William O. Parker, Jr.

GAC/php Attachments cc: Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Mr. P. R. Bemis NRC Resident Inspector McGuire Nuclear Station 4

l

'l Attachment A McGUIRE NUCLEAR STATION - UNIT 1 NRC/FRC REQUEST FOR INFORMATION B.I.a TMI Action Plan Equipment Installed as of January 1, 1981 1.

Reactor Vessel Head Vents (II.B.1) 2 '.

Pressurizer Relief / Safety Valve Position Indication (II. D.3 )

3.

Emergency Power to Pressurizer Heaters (II.E.3.1) 4.

Containment Isolation Provisions (II.E.4.2) 5.

Subcooling meter (II.F.2) 6.

Power Supply for PORV's, Block Valves and Pressurizer Level Instruments (II.G.1) 7.

Modify PORV Integral-Derivative Controller (II.K.3.9)

B.I.b TMI Action Plan Equipment installed af ter January 1, 1981 1.

Post Accident Sampling (II.B.3) 2.

Auxiliary Feedwater Initiation and Indication (II. E.1. 2) 3.

Additional Accident Monitoring Instrumentation (II. F.1 )

4.

Reactor Vessel Level Instrument System (II.F.2) 5.

Reactor Trip on Turbine Trip (II.K.3.12) e

-7 Attachment B 1 of 2 McGUIRE NUCLEAR STATION - UNIT 1 NUREG 0588 NRC/FRC REQUEST FOR INFORMATION B.I.c Correlation of Equipment items with Specific Sections of NUREG 0737 0737 SECTION/DESCRIPTlON EQUIPMENT IDENTIFICATION COMMENTS II.E.1.2 Auto initiation of the Aux.

Not Listed Equipment additions located in a FDW System mild environment.

Aux. FDW Flow Indication Lambda LCS Power Supply This equipment is not required for accidents that affect its environment.

Ohmite Brown Devil This equipment is not required Resistor for accidents that affect its environment.

Samuel Moore Instrumen-See Attachment C; p. 34H & 45R tation Cable-EP/Hypalon insulation Okonite Instrumentation See Attachment C; p. 35H & 41R and Control Cable-EP (Report N1 only)

Insulation II.E.4.2 Containment isolation Not Listed Equipment additions located in a Provisions mild environment.

II.E.3.1 I

Emergency Power to Not Listed No equipment additions for this Pressurizer Heaters item.

II.G.1 Power Supply for PORV's, Not Listed No equipment additions for this Block Valves and item.

Pressurizer Level Instru-l ments.

1 l

i d

Att chment B 2 cf 2 0737 SECTION/ DESCRIPTION EQUIPMENT IDENTIFICATION COMMENTS II.F.2 Subcooling Meter Not Listed RTD's and pressure transmitters are not an addition for this item.

Core Exit Thermocouples are not safety related.

R: actor Vessel Level Westinghouse RVLIS See Attachment C; p. 35C Instrumentation System Okonite Instrumentation See Attachment C; p.

17A, 35H &

Control Cable - EP 41R, (Report H1 only)

Insulation Samuel Moore Instrumen-See Attachment C; p. 34H & 45R tation Cable - EP/Hypalon insulation Brand Rex instrumentation See Attachment C; p. 27C Cable - XLPE Insulation II. D. 3 Pressurizer Rellef/ Safety TEC Acoustical Valve See Attachment C; p. 34C Valve Position Indication Position Monitoring System Samuel Moore Instrumenta-See Attachment C; p.

13A & 28C tion Cable-EP/Hypalon insulation Okonite Instrumentation See Attachment C; p. 35H & 41R, and Control Cable-EP (Report N1 only)

Insulation II.B.3 Post Accident Sampling Not Listed Equipment additions located in a mild environment.

II.E.4.1 Dedicated H2 Penetrations Not Listed This item is not applicable to McGuire.

II.K.3.12 Rractor Trip on Turbine Not Listed Equipment additions located in Trip a mild environment.

II.K.3.9 Modify PORV Integral-De-Not Listed No equipment additions for this rivative Controller item.

A

e Attachment D 1 of 7 McGUIRE NUCLEAR STATION - UNIT I NUREG 0588 NRC/FRC REQUEST FOR INFORMATION 8.1.e Environmental Proflies and Service Conditions inside Containment The overall worst-case Containment accident temperature and pressure time histories are as follows:

Temperature (Upper Containment):

time history is shown in FSAR Figure 6.2.1-24, Rev. 36 (Attached).

Temperature (Lower Containment):

time history for the first 1000 seconds is shown in FSAR Supplement 1, Q042.73, Figure 7, Rev. 39 (Attached). Af ter 20 minutes, FSAR Figure 6.2.1-25, Rev. 36 (Attached) j is the limiting time history.

Pressure (Upper and Lower Contal nment): time history is shown in FSAR Figure 6.2.1-23, Rev. 36 (Attached).

J The maximum normal operating temperature inside Containment is 120*F.

Annulus The overall worst-case Annulus temperature excursion is due to a Main Steam Line Break inside Containment. - The time history (Attached) is shown in Duke calculation MCC-1223.14-00-0006.

The maximum normal operating temperature in the Annulus is 104*F.

1 Aux 111ary Buildinq The temperature time history for pipe rupture steam environments (HELB) is shown in the Plant Environmental Parameters manual, Figure 6.0-1 (Attached).

Maximum normal operating temperature in the Auxiliary Building is 130*F.

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l FIGURE 6.0-1 ficGUIRE flVCLEAR STATION I

Temperature Decay Curve for Pipe Rupture Steam Environments Outside Containment T2 C

2-u a

UE T) l5 EW I

I 30 150 TIllE (Min)

T) - compartment particular normal steady state temperature (reference Section 7.0).

T peak pipe rupture steam environment temperature in'~the compartment 2-of interest (reference Table 6.0-1)

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Attachment D II.6.0-6 7 of 7

Attcchment E I of 2 McGUIRE NUCLEAR STATION - UNIT 1 NUREG 0588 NRC/FRC REQUEST FOR INFORMATION B. I.f Approximate Installation Dates of THI Action Plan items item Approximate Installation Date II.B.1 Reactor Vessel Head Vents September 1980 II.B.3 Post Accident Sampling December 1981 II.D.3 Pressurizer Relief / Safety Valve June 1980 Position Indication II.E.1.2 Auxiliary ' Feedwater initiation February 1981 Auxiliary Feedwater Indication June 1980 II.E.3.1 Emergency Power to Pressurizer Heaters No equipment additions for this item II.E.4.2 Containment isolation Provisions May 1980 II.F.1 Containment Radiation Monitor June 1981 Containment Pressure Indication February 1981 Containment Hydrogen.Concent ration June 1981 Containment Water Level Indication February 1981 Unit Vent Radiation Monitor June 1981 Unit Vent Flow Meter March 1981 II.F.2 Subcooling Meter No equipment additions for this ites Reactor Vessel Level Instrumentation System December 1982 O

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

.Attechment E i 2,9,f 2.,

e Approximate Installation Date item II.G.1 Power Supply for PORV's, Block Valves and No equipment additions for this item Pressurizer Level Instruments II.K.3.9 l

Modify PORV Integral-Derivative Controller No equipment additions for this item II.K.3.12 Reactor Trip on Turbine Trip May 1981 d

9 e

Attachment A McGUIRE NUCLEAR STATION - UNIT I NRC/FRC REQUEST FOR INFORMATION 8.1.a TMI Action Plan Equipment instslied as of January 1, 1981 1.

Reactor Vessel Head Vents (II.B.1) 2 Pressurizer Rollef/ Safety Valve Position Indication (II. D. 3 )

3 Emergency Power to Pressurizer Heaters (II.E.3.1) 4.

Containment isolation Provisions (II.E.4.2) 5 Subcooling meter (II.F.2) 6.

Power Supply for PORV's, Block Valves and Pressurizer Level Instruments (II.G.1) 7.

Modify PORV Integral-Derivative Controller (II.K.3.9)

B.I.b TMI Action Plan Equipment Installed af ter January 1,1981 1.

Post Accident Sampling (II.B.3) 2.

Auxiliary Feedwater initiation and Indication (II. E.1. 2 )

3.

Addi tional Accident Monitoring Instrumentat ion (II.F.1) 4 Reactor Vessel Level Instrument System (II. F. 2 )

5.

Reactor Trip on Turbine Trip (II.K.3.12)

Attcchment B 1 of 2 McGUIRE NUCLEAR STATION - UNIT 1 NUREG 0588 NRC/FRC REQUEST FOR INFORMATION B.I.c Correlation of Equipment items with Specific Sections of NUREG 0737 0737 SECTION/ DESCRIPTION EQUIPMENT IDENTIFICATION COMMENTS II.E.1.2 Auto initiation of the Aux.

Not Listed Equipment additions located in a FDW System mild environment.

Aux. FDW Flow Indication Lambda LCS Power Supply This equipment is not required for accidents that af fect its environment.

Ohmite Brown Devil This equipment is not required Resistor for accidents that affect its environment.

SamucI Hoore Instrumen-See Attachment C; p. 34H & 45R tation Cabic-EP/Hypalon Insulation Okonite Instrumentation See Attachment C; p. 35H & 41R and Control Cable-EP (Report N1 only)

Insulation II.E.4.2 Containment Isolation Not Listed

" Equipment additions located in a Provisions mild environment.

II.E.3.I Emergency Power to Not Listed No equipment additions for this Pressurizer Hecters item.

II. G.1 Power Supply for PORV's, Not Listed No equipment additions for this Block Valves and item.

Pressurizer Level Instru-ments.

I e

P Attcchment B 2 cf 2 0737 SECTION/ DESCRIPTION EQUIPMENT IDENTIFICATION COMMENTS II.F.2 Subcooling Heter Not Listed RTD's and pressure t ransmitters are not an addition for this item.

Core Exit Thermocouples are not safety related.

Reactor Vessel Level Westinghouse RVLIS See Attachment C; p. 35C Instrumentation System Okonite Instrumentation See Attachment C; p.

17A, 35H &

Control Cable - EP 41 R, (Report N1 only)

Insulation Samuel Moore instrumen-See Attachment C; p. 34H & 45R tation Cable - EP/Hypalon Insulation Brand Rex Instrumentation See Attachment C; p. 27C Cable - XLPE Insulation II.D.3 Pressurizer Relief / Safety TEC Acoustical Valve See Attachment C; p. 34C Valve Position Indication Position Monitoring System Samuel Moore Inst rumenta-See Attachment C; p.

13A & 28C tion Cable-EP/Hypalon insulation Okonite Instrumentation See Attachment C; p. 35H & 41R, and Control Cable-EP (Report N1 only)

Insulation II.B.3 Post Accident Sampilng Not Listed Equipment additions located in a mild environment.

II.E.4.1 Dedicated H2 Penetrations Not Listed This item is not applicable to McGuire.

II.K.3.12 R: actor Trip on Turbine Not Listed Equipment additions located in Trip a mild environment.

II.K.3.9 Modify PORV Integral-De-Not Listed No equipment additions for this rivative Controller item.

o McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 27c

SUMMARY

OF.ENVIRONMENTALQUALIFICATIONOFCLASS1EEQUIPMENT Rev. 0 >

LOCATED INSIDE CONTAINMENT EQUIPMENT ID:

Cable -

MANUFACTURER:

Brand Rex MODELi:~'XLPEInsulation.

(1)

Control (Lower Containment)

ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTitATED (2)

QUALIFIED ACCIDENT

(% OF SPAN)

(% OF SPAN)

ENVIP,0NMENT(3)

Temp:

327 F Temp:

346'F 30 days 120 days N/A' N/A Press:

14.8 psig Press:

113 psig post DBE post DBE RH:

100%

RH:

100%

7 8

Rad:

7.5X10 R Rad:

2X10 R Chem Spray: Boric Chem Spray: Boric acid and sodium acid and sodium

~

tetraborate soln.

hydroxide soln.

~

6200 ppm Boron 10 pH QUALIFICATION REPORT (4):

Test Reports FC5120-1 and FC5120-3

~

METHOD:

Test

^

EL40101T/28 - 4/13/82 Attachment C 1 of 18

's

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 28c

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED INSIDE CONTAINMENT EQUIPMENT ID:

Cable -

MANUFACTURER:

Samuel Moore MODEL #:

EP/Hypalon Insulation (1)

Instrumentation (Lower Containment)

ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED-DEMONSTRATED (2)

QUALIFIED ACCIDENT

(% OF SPAN)

(% OF SPAN)

ENVIRONMENT (3)

Temp:

327 F Temp:

340 F 30 days 30 days N/A N/A Press:

14.8 psig Press:

105 psig post DBE post DBE RH:

100%

RH:

100%

Rad:

7.SX107R Rad:

2X10sR Chem Spray: Boric Chem Spray: Boric acid and sodium acid and sodium tetraborate soln.

hydroxide soln.

2000 ppm Boron, 9-11 pH QUALIFICATION REPORT (4):

Test Report F-C3683 METHOD:

Test EL40101T/29 - 4/13/82 Attachment C 2 of 18 u

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 34c

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED INSIDE CONTAINMENT EQUIPMENT ID:

Acoustical Valve Position MANUFACTURER:

TEC MODEL #:

1414 (1)

Monitors-accerometers, charge converters and cables (Lower Containment)

ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2)

QUALIFIED ACCIDENT

(% OF SPAN)

(% OF SPAN)

ENVIRONMENT (3)

Temp:

327 F (Note 16) 2 weeks (Note 16)

N/A (Note 16) 100% psig post DBE Press:

14.8 RH:

Rad:

8X107R Chem Spray: Boric acid and sodium tetraborate soln.

QUALIFICATION REPORT (4):

(Note 16)

METHOD:

(Note 16)

EL40101T/35 - 4/13/82 Attachment C 3 of 18

4 i

Page 35c McGUIRE NUCLEAR STATION - UNITS 1 AND 2

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED INSIDE CONTAINMENT I

EQUIPMENT ID:

Reactor Vessel MANUFACTURER: Westinghouse MODEL #:

RVLIS (1)

Level Instrumentation System (Lower Containment)

ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2)

QUALIFIED ACCIDENT

(% OF SPAN)

(% OF SPAN)

ENVIRONMENT (3)

The qualification information for the In-Containment portions of this' system will be provided in a future revision of this submittal following review by Duke Power Company.

QUALIFICATION REPORT (4):

N/A METHOD:

N/A

,. EL40101T/36 - 4/13/82 Attachment C 4 of 18

Page 36c Revision 0 MCGUIRE NUCLEAR STATION - UNITS 1 AND 2 ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT LOCATED INSIDE CONTAINMENT Note 1 All equipment identified in this table is located inside the containment, specifically in the lower compartment except for the electric hydrogen recombiner, containment air return fan motors, hydrogen skimmer fan motors, containment air return isolation damper motors, differential pressure switches for damper control, Limitorque valve motor operators and cables associated with these devices.

Note 2 The parameters that compose the overall worst-case containment accident environment are as follows:

Temperature (Upper Containment):

180F peak; time history as shown in FSAR Figure 6.2.1-24 (Rev. 36).

Temperature (Lower Compartment):

327F peak; time history as shown in FSAR Supplement 1, Q042.73, Figure 7 Revision 39.

Pressure (Upper and Lower Compartment):

14.8 psig peak; time history as shown in FSAR Figure 6.2.1-23 (Rev. 36).

Relative Humidity:

100%

Radiation:

Total integrated radiation dose for the equipment location includes 40 year normal operating dose plus the appropriate accident dose (except for the narrow-range and wide-range RTD's).

Chemical Spray:

Boric acid and sodium tetraborate spray resulting from mixing in the containment sump of borated water from the RWST and sodium tetraborate solution from ice bed melt.

Concentrations are as follows:

Initial Spray:

2000 - 2100 ppm Boron 4.0 - 4.7 pH

~

Recirculation Spray:

1800 - 2200 ppm Boron 6.0 - 10.0 pH Note 3 Equipment operability requirements in the containment accident environment are as identified in FSAR Table 3.11.1-1 (Rev. 25).

Note 4 Environmental Qualification test reports for the following equipment have previously been submitted to the NRC Staff:

EL40101T/37 - 4/13/82 Attachment C 5 of 18

Page 37c Revision 0 1

Transmitter-Barton (by Westinghouse)

RTD's-Rosemount (by Westinghouse)

Electric Hydrogen Recombiner (by Westinghouse) i Containment Air Return Fan Motors (by Duke) l Hydrogen Skimmer Fan Motors (by Duke)

Solenoid Operators-Valcor (by Duke)

Electric Penetrations (by Duke)

Cable Termination / Splice Material (by Duke)

Stem-Mounted Limit Switches (by Duke)

Cable Entrance Seal Material (by Duke) i l

Note 5 i

A requirement for McGuire is to limit the positive error for the trip

~

function of narrow-range steam generator level transmitters to +5%.

The original Lot 2 report noted an error of +7.3% early in the steam test l

transient.

Additional tests were performed on the same unit using water as the process medium instead of nitrogen.

This caused the temperature of the strain gage to track the temperature of the circuit board more closely 1

i during the first minute and limited the positive error to less than 4%. In i

other words, the temperature difference between the strain gage and the circuit board has been reduced to a level compatible to McGuire functional i

requirements.

Note 6 1

This equipment is located in Unit 2 which is scheduled for operation in 4

j 1983.

Qualification information will be provided in a future revision to this submittal following review by Duke Power Company.

4 Note 7 Five minutes is adequate time to assure containment isolation and the required repositioning of other safety-related valves.

Note 8 During the 30 days following a postulated accident, the containment temperature and pressure will approach normal; therefore, additional l

service can reasonably be expected from this equipment.

m Note 9 The Target Rock solenoid valves are used in the reactor head vent system to provide a path for removal of non-condensable gases.

Core events leading to the generation of significant amounts of non-condensable gases occur early in the postulated accident sequences and are of short duration; therefore, these valves are only required to operate within the first few days of the accident.

The need for venting non-condensable gases is not anticipated beyond the 14 day qualification of the valves.

EL40101T/38 - 4/13/82 Attachment C 6 of 18

i Page 38c Revision 0 Note 10 Electric penetration types B, C, F, G, and K are the only penetrations required to function electrically in the containment accident environment.

l All electric penetrations, however, are designed and qualified to maintain their mechanical integrity under normal and postulated accident environmental ccnditions.

Note 11 The McGuire electric penetrations are protected from direct spray impingement by galvanized steel boxes.

Note 12 The manufacturer's test report states that the detector assembly is constructed of F.etal and ceramic and is not affected by radiation.

Note 13 This equipment has been installed per NRC requirements stated in NUREG 0737.

Overall system accuracy should be within a factor of 2 over the entire range as stated in Regulatory Guide 1.97, rev. 2*.

The calibrated accuracy of the system is 20% of the system's range.

Note 14 The cables for the containment radiation monitors (high range) which are located inside the containment are routed in conduit, and, therefore not exposed to chemical spray.

l Note 15 L

Subsequent testing by the manufacturer showed a failure of a sample of cable at a higher temperature.

Duke Power Company will replace the existing cable by June 1982 with a cable having a higher temperature qualification.

Note 16 This equipment has been installed per.NRC requirements stated i.n NUREG0737.

Qualification information will be provided in a future revision to this submittal following review by Duke Power Company.

i EL40101T/39 - 4/13/82 Attachment C 7 of 18

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 13A

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED IN THE ANNULUS EQUIPMENT ID:

Cable - Instrumentation MANUFACTURER:

Samuel Moore MODEL #:

EP/HYP ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1)

QUALIFIED ACCIDENT (2)

(% OF SPAN)

(% 0F SPAN)

ENVIRONMENT Temp:

142 F Temp:

194 F 4 months 1 year N/A N/A RH:

100%

RH:

100%

post DBE post DBE 7

Rad:

3X10 R Rad:

2X108R (Note 5)

QUALIFICATION REPORT:

Samuel Moore Test FC3683 METHOD:

Test e

EL40101T/53 - 4/13/82 Attachment C 8 of 18

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 17A

SUMMARY

OFENVIRONMENTALQUALIFICATIONOFCLASS1EEQUIPAENT Rev. O LOCATED IN THE ANNULUS EQUIPMENT ID:

Cable - Instrumentation MANUFACTURER:

Okonite MODEL #:

EP ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1)

QUALIFIED ACCIDENT (2)

(% OF SPAN)

(% OF SPAN)

ENVIRONMENT

)

Temp:

142 F Temp:

194 F 4 months 1 year N/A N/A RH:

100%

RH:

100%

post DBE post DBE Rad:

3X107R Rad:

2X108R (Note 5) i QUALIFICATION REPORT:

Okonite Test Reports N1, FN1 & G3 METHOD:

Test EL40101T/57 - 4/13/82 Attachment C 9 of 18

\\

Page 23A Revision 0 MCGUIRE NUCLEAR STATION - UNITS 1 AND 2 ENVIRONMENTAL QUALFICATION OF CLASS 1E EQUIPMENT LOCATED IN THE ANNULUS Note 1 The parameters that compose the overall worst-case annulus accident environment are as follows:

Temperature: 142 F peak; Annulus temperature excursion due to a main steam lige break inside containment as shown in calculation MCC-1223.14-00-0016.

t Relative Humidity: 100%

Radiation:

Total integrated radiation dose for the equipment location includes 40 years normal operating dose plus the appropriate accident dose.

The accident dose is a function of the operability time required in the accident environment.

Note 2 The operability time demonstrated is the period required for the equipment i

to rbach its qualified radiation dose in the accident environment.

Temperature transients in the annulus, due to a MSLB (142 F) or LOCA (122 F) inside containment, are minimal and well within the design capabilities of the equipment.

Therefore, temperature is not a factor in operability time.

1 Note 3 Five minutes is adequate time to assure containment isolation and the required repositioning of other safety related valves.

Note 4 This transmitter is located in Unit 2 which is scheduled for operation in l

1983.

Qualification information will be provided in a future revision to this submittal following review by Duke Power Company.

Note 5 The qualified temperature is based on the insulation rating of the cable.

The temperature of the insulation is a function of the cable conductor temperature and the ambient temperature.

EL40101T/63 - 4/13/82 Attachment C 10 of 18 l

McGUIRE NUCLEAR STATION UNITS 1 AND 2

[

Page 3411

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 0 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID:

Cable - Instrumentation MANUFACTURER:

Samuel Moore MODEL #:

EP/Hypalon Insulation HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY:

ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1)

QUALIFIED HELB

(% OF SPAN)

(% OF SPAN)

ENVIRONMENT (2)

Temp:

330 F Temp:

340 F Continuous Continuous N/A N/A (Note 6)

QUALIFICATION REPORT:

Test Report F-C3683 METHOD:

Test Attachment C 11 of 18 EL40101T/98 - 4/13/82

~ _.

McGUIRE NUCLEAR STATION ' UNITS 1 AND 2

[

Page 35H

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID:

Cable - Control, Instrumentation, MANUFACTURER:

Okonite MODEL #:

EP Insulation and 2KV power HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1)

QUALIFIED HELB

(% OF SPAN)

(% OF SPAN)

ENVIRONMENT (2)

Temp:

330 F Temp:

345 F Continuous Continuous N/A N/A (Note 6) l QUALIFICATION REPORT:

Test Reports FN-1, N-1, G-3, 110E and 141 METHOD:

Test Attachment C 12 of 18 EL40101T/99 - 4/13/82

m.. _

~ ~ ~

Page 65H Revision 0 MCGUIRE NUCLEAR STATION UNITS 1 AND 2 ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT Note 1 The methods employed to evaluate pipebreaks and to determine and resulting environmental parameters are discussed in Duke Power Company Report MDS/PDG-77-1.

The Evaluation of the Effects of Postulated Pipe Failures Outside Containment for McGuire Nuclear Station.

I Note 2 The HELB environment is assumed to exist for 2h hours based on 30 minutes 3

at the peak temperature after which action by the operator isolates the i

break and allows Auxiliary Building temperature to decrease to normal ambient in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Note 3 i

Rotork Test Report TR-3025 shows that when the qualified temperature for these valves is exceeded, the torque switches may fail on the next operation of the valves.

Since at least one additional operation is available after the valve's temperature qualification has been exceeded, the valve can be relied upon to move to its safety position.

Note 4 The test was conducted for 30 minutes, however, the Class 1E solenoids which operate the FWIV's de-energize upon initiation of containment isolation and allow the FWIV's to close within 5 seconds.

With the solenoid valves de-energized, the FWIV's will remain in a closed position indefinitely.

Note 5 i

A qualification program is currently being developed for these components.

The result of this program will be reported upon completion.

Test I

completion is expected by 6/30/82.

l

{

Note 6 I

The HELB analysis has identified pipe breaks resulting in higher temgeratures;however,therearenocablesexposedtotemperaturesabove 1

330 F.

Note 7 The com'ponents listed are general application devices.

These components are installed in metal enclosures and depending on their specific design application, may be located in various areas of the Auxiliary Building.

This table addresses the qualfication of these components with respect to the worst-case pipe break environment applicable to the components EL40101T/129 - 4/13/82 Attachnaent C I3 0f Io -

J

Page 66H L

Revision 0 location.

Note 8 The qualified operating temperature is based on the maximum current flowing through the fuse or resistor and appropriate fuse or resistor derating.

1 Note 9 The only requirement of the optical isolator is to retain its input f

integrity during the accident.

Note 10 Accuracy demonstrated is the shift in the actual resistance due to the i

change in temperature during the accident.

L l

l l

i d

4 I

t EL40101T/130 - 4/13/82 Attachment C i

14 of 18

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 41R

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION ENVIRONMENT EQUIPMENT ID:

Control, Instrumentation MANUFACTURER:

Okonite MODEL #:

EP Insulation (1)

Cable RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2)

(TID) 1.1X108 RAD 2X10sRAD QUALIFICATION REPORT: Okonite Test Reports FN-1, G-3, N-1, 110E and 141 METHOD:

Test ei EL40101T/172 - 4/13/82 Attachment C 15 of 18

Page 45R McGUIRE NUCLEAR STATION - UNITS 1 AND 2

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION ENVIRONMENT EQUIPMENT ID:

Instrumentation Cable MANUFACTURER:

Samuel Moore MODEL #:

EP/Hypalon Insulation (1)

RECIRCULATION RADIATION RADIATION LEVEL lTO WHICH ENVIRONMENT QUALIFIED (TID) (2)

(TID) 1.1X10sRAD 2X108 RAD i

QUALIFICATION REPORT:

Samuel Moore Test Report F-C3683 1

METHOD:

Test EL40101T/176 - 4/13/82 Attachment C 16 of 18 m

Page 61R Revision 0 MCGUIRE NUCLEAR STATION - UNITS 1 AND 2 ENVIRONMENTAL QUALFICATION OF CLASS 1E EQUIPMENT LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO POST-LOCA RECIRCULATION RADIATION ENVIRONMENT Note 1 Class 1E equipment that is exposed to the post-LOCA recirculation radiation environment has been evaluated for proper radiation qualification and is included in this table if it is exposed to a total integrated dose ' equal to or greater t.han 1 x 103 RAD.

A total integrated dose (i.e., forty year normal plus one year accident radiation dose) of less than 1 x 103 RAD is considered negligible since_no materiais have been identified at McGuire

_ that s hibit-a significant aging mechanism when exposed to less than 1x103 RAD.

Note 2 The recirculation radiation environment consists of the forty year normal operating radiation dose plus the dose received from one year of post-LOCA reactor coolant recirculation.

Note 3 The McGuire 600 volt load centers are qualified by similarity to 600 volt load centers at Oconee Nuclear Station as reported in Report Number 0M-301-80.

Note 4 Radiation testing of this equipment is not required for levels below 1x104 RAD per Section 8.1 of IEEE 535-1979.

Note 5 A qualification program is currently in progress for these components.

The results of this program will be reported upon receipt and review of the qualification documentation, which is expected in August 1982.

Note.6 The compodgnts listed are general application devices.

These components are installed in metal type enclosures and depending on their specific design application, may be located in various areas of the Auxiliary Building.

This table addresses the qualification of these components with respect to the worst-case radiation environment (40 year normal dose plus 1 year post-LOCA)' applicable to the components location.

EL40101T/61 - 4/13/82 Attachment C 17 o f 1_8 __ __ _

__ o

O a

Page 62 R Rev. 0 Note 7 These components are located in enclosures in both Units 1 and 2.

Presently, the components exposed to a post-LOCA recirculation radiation greater than 1x103 RAD and used in Unit 1 Class 1E circuitry are gualified by TR-040.

The radiation qualification of Unit 2 components is in progress.

The results of this qualification program will be provided upon completion by Duke Power Company.

i i

I EL40101T/193 - 4/13/82 Attachment C 18 of i8

i Attachment D McGUlRE NUCLEAR STATION - UNIT 1 NUREG 0588 NRC/FRC REQUEST FOR INFORMATION B.I.e Environmental Frofiles and Service Conditions inside Containnent The overall worst-case Containment accident temperature and pressure time histories are as follows:

Tempe ratu re (Upper Containment):

time history is shown in FSAR Figure 6.2.1-24, Rev. 36 (Attached).

Tempe rat u re (Lower Containment):

time history for the first 1000 seconds is shown in FSAR Supplement 1, Q042.73, Figure 7, Rev. 39 (Attached). Af ter 20 minutes, FSAR Figure 6.2.1-25, Rev. 36 (Attached) is the limiting time history.

Pressu re (Upper and Lower Contai nment): time history is shown in FSAR Figure 6.2.1-23, Rev. 36 (Attached).

The maximum normal operating temperature inside Containment is 120 F.

Annulus The overall worst-case Annulus temperature excursion is due to a Main Steam Line Break inside Containment. The time history (Attached) is shown in Duke calculation MCC-1223.14-00-0006.

The maximum normal operating temperature in the Annulus is 104 F.

Auxiliary Building The temperature time history for pipe rupture steam environments (HELB) is shown in the Plant Environmental Parameters manual, Figure 6.0-1 (Attached).

Maximum normal operating temperature in the Auxiliary Building is 130 F.

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FIGURE 6.0-1 ficGUIRE NUCLEAR STATION l

Temperature Decay Curve for Pipe Rupture Steam Environments Outside Containment T2 C

U T) w5 e

i I

I 30 150 TittE (Min) j-compartment particular normal steady state temperature (reference T

Section 7.0).

T peak pipe rupture steam environment temperature in the compartment 2-of interest (reference Table 6.0-1)

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11.6.0-6 7 of 7

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Attechment E 1 of 2 McGUIRE NUCLEAR STATION - UNIT 1 NUREG 0588 NRC/FRC REQUEST FOR INFORMATION B. I.f Approximate Installation Dates of TMI Action Plan items Item Approximate Installation Date II.B.1 Reactor Vessel Head Vents September 1980 II.B.3 Post Accident Sampling December 1981 II.D.3 Pressurizer Relief / Safety Valve June 1980 Position Indication II.E.1.2 Auxil iary Feedwater Initiation February 1981 Auxiliary Feedwater Indication June 1980 II.E.3.1 Emergency Power to Pressurizer Heaters No equipment additions for this item II.E.4.2 Containment I solation Provisions May 1980 II.F.1 Containment Radiation Monitor June 1981 Containment Pressure Indication February 1981 Containment Hydrogen Concentration June 1981 Containment Water Level Indication February 1981 Unit Vent Radiation Monitor June 1981 Unit Vent Flow Meter March 1981 II.F.2 Subcooling Meter No equipment additions for this item Reactor Vessel Level Instrumentation System December 1982 P

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Attachment E 2 of 2 Item Approximate Installation Date II. G.1 Power Supply for PORV's, Block Valves and No equipment additions for this item Pressurizer Level I nst rumen t s II.K.3.9 Modify PORV Integral-Derivative Controller No equipment additions for this item II.K.3.12 Reactor Trip on Turbine Trip May 1981 l

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