Text

Forwards Rev to NUREG-0588 Submittal Re Environ Qualification of Electrical Equipment.General Update of Equipment Tables & Consolidation of Certain Qualification Info Provided
	ML20093L526
Person / Time
Site:	Mcguire, McGuire
Issue date:	10/15/1984
From:	Tucker H; DUKE POWER CO.
To:	Adensam E, Harold Denton; Office of Nuclear Reactor Regulation
References
	RTR-NUREG-0588, RTR-NUREG-588 NUDOCS 8410190045
	Download: ML20093L526 (269)
	v • d • e

a d'

DUKE POWER GOMPAhT P.O. HOX 33180 CHARLOTT!*, N.O. 28242 HAL B. TUCKER TELEPHONE gion rae=y_

(704) 073-4531 Cetober 15, 1984 l

l Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. 3. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief Licensing' Branch No. 4

Subject:

McGuire Nuclear Station Docket Nos. 50-369, 50-370

Dear Ms. Adensam:

Please find attached the latest revision of Duke's NUREG-0588 submittal for McGuire Nuclear Station. The purpose of this revision is to provide a general update of the equipemtn tsbles as well as to consolidate certain qualification information (e.g., the McGuire TER Response) into the McGuire NUREG-0588 submittal. The following major areas of revision should be noted:

1. The introduction has been revised to include Duke Power Company's response to open items identified in the Franklin Research Center Technical Evaluation Report (TER) concerning environmental qualification of electrical equipment for McGuire Nuclear Station.

With specific regard to TER Items 31, 47, and 77, justifications for interim operation (JIO's) previously submitted have been resolved. The JIO covering TER Items 3, 4, 5, and 7 (Valcor Solenoid valves) has been updated.

2. The introduction has also been revised to include Duke Power Company's response-to 10CFR50.49(b).

3. Attachments 6. 7, 8, and 9 of the NUREG-0588 submittal have been deleted for consolidation purposes. The information in these attachments has been incorporated into the equipment summary sheets and/or placed into the appropriate equipment qualification files.

4. Attachment 3 has been reviced to reflect the environmental parameters resulting from a new analysis for a main steam line break in the doghouse.

If there are any questions regarding this, please advise through normal licensing channels.

V ry truly yours, gg # *

.Hal B. Tucker 8410190045 841015 %$

PDR ADOCK 05000369 g _

P PDR , _ _ _ . _ _ _ _ _. _

s

o

. Mr. Harold R. Denton, Director

' October 15, 1984 Page Two RLG/mjf.

-Attachment-cc: 'Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission I

Region II _

101 Marietta Street, NW, Suite 2900 t Atlanta,-Georgia 30323 W. T. Orders NRC Resident Inspector McGuire Nuclear Street

Mr. Ralph Birkel

' Division of Project Management Office of Nuclear Reactor Regulation

U.~ S. Nuclear Regulatory Commission Washington, D. C. 20555 t"

,NY b

I r

1 f

a f - - w y- gv.- yms-w y..- t--- T Tv --

-T vT y ""-r*y --ere- -- =m- y 9 -- , -

i ,.

MCGUIRE NUCLEAR STATION - UNITS 1 AND 2 ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT In accordance with 10CFR50.49.and the Category II guidelines of NUREG-0588, Duke Power Company is providing the information in this submittal to demonstrate that electrical equipment required to perform a safety-related function in a harsh environment is environmentally qualified.

In addition to equipment specific infonnation, this submittal also contains a discussion on compliance with 10CFR50.49(.b) and Duke's response and resolutions to open items identified in the Franklin s- Research Center Technical Evaluation Report (TER).

With regard to the fonnat of this submittal, the information described above.is arranged as follows:

0 Introduction, Discussion of 10CFR50.49(.b) and Response and Resolu-tions to Open Items Identified in the Franklin Research Center Technical Evaluation Report (.TER).

8 Attachment 1 - Summary of Environmental Qualification of Class 1E

- Equipment Located Inside Containment 0 - Attachment 2 - Summary of Environmental Qualification of Class lE Equipment Located in the Annulus e Attachment 3 - Summary of Environmental Qualification of Class lE

, Equipment Located Outside Containment and Exposed to HELB Environment 8 - Attachment 4 - Summary of Environmental Qualification of Class lE Equipment Located Outside Containment and Exposed to the Post-LOCA

. Recirculation Radiation Environment 8 Attachment 5 - Duke Power Company Position on the Category II Guidelines of- NUREG-0588

!' Attachments 1, 2, 3, and 4 provide a tabular listing of Class lE equipment L exposed to harsh environment and inicude appropriate qualification data l- for the equipment. Attachment 5 provides the Duke Power Company position on the Category II Guidelines of NUREG-0588.

1

MCGUIRE NUCLEAR STATION - UNITS 1 AND 2 ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT COMPLIANCE WITH 10CFR50.49(b)

In response to .10CFR50.40(.b) Environmental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants, Duke Power Company is providing.the following information:

With regard to 10CFR50.49(b)(1), safety-related electrical equipment located

- in a harsh environment is identiffed in Duke Power Company's NUREG-0588 submittal for the McGuire Nuclear Station.

With regard _to 10CFR50.49(b)(2), Duke Power Company has not identified any non-safety-related electrical equipment located in a harsh environment whose failure under the postulated accident conditions could prevent satisfactory accomplishment of a safety function by safety-related equip-ment. This determination was based on a review of Duke's design practices for McGuire, the McGuire electrical and physical separation criteria, and previous reviews in this area with regard to IE Information Notice 79-22.

The McGuire safety-related electrical power and control systems are designed in accordance with Institute of Electrical and Electronics Engineers (.IEEE)

Std. '08-1971 J and IEEE Std. 279-1971, respectively, as discussed in the McGuire Final Safety Analysis Report (FSAR). These two standards, as implemented in the McGuire design, place strict requirements on the inter-

. facing of safety-related and nonsafety-related electrical equipment. Nonsafety-related loads receiving power from safety-related buses are automatically tripped from these buses by safety-related breakers, receiving trip signals generated by the plant protection systems, in order to preclude unacceptable influences of nonsafety-related equipment on the safety-related power system.

The McGuire separation requiremerts are discussed in FSAR Section 8.3.1.2.7 and have previously been reviewed and accepted by the staff (see McGuire SSER 2).

With regard to control systems where nonsafety-related equipment provides input to control safety-related equipment, accident actuation signals are provided to override the nonsafety-related control inputs. In addition to the override feature, nonsafety-related inputs to safety-related control systems are reviewed during the design process to ensure that no failure modes of the nonsafety-related inputs can preclude completion of the required safety actuation. The combinatien of the override feature and the review of nonsafety-related control

- inputs ensures thst no unacceptable influences of nonsafety-related equipment on safety-related equipment can occur to prevent the satisfactory accomplish-ment of a safety function.

In addition to the design features described above, Duke Power Company performed an analysis of control systems at McGuire in response to Office of Inspection and Enforcement (IE) Information Notice 79-22. The purpose of the analysis

--was to determine what, if any, design changes or operctor actions would be necessary to ensure that environments caused by high energy line breaks would not cause an electrical nonsafety-related control system to fail in such a manner as to complicate the event beyond the assumptions of the accident analysis.

The systems considered in this analysis were identified by Westinghouse for McGuire and reviewed by the licensee for the interaction described above. The 4 systems reviewed were the steam generator power-operated relief valve (PORV)

_ control system, the pressurizer PORV control system, the main feedwater control

4

. system, and the. automatic rod control, system. The results of this review for McGuire revealed that no design changes c- operator actions were required

' to address the issue. Duke Power Company has recently documented the same

' analysis with the same results for the _ Catawba Nuclear Station in response to NRC Staff Question 420.3. The~ staff has reviewed the information provided and found the Catawba analaysis acceptable (see Catawba SER (NUREG-0954)).

' This issue is also being addressed by the NRC as an Unresolved Safety Issue 1 (A-47). Duke Power Company,fs following the status of this issue and will 1 take action as appropriate when this issue is resolved. l i

F . With . regard to 10CFR50.49(b)(3), McGuire Technical Specification Table 3.3-10 1,dentifies accident monitoring instrumentation and serves as the basis for accident monitoring requirements. The items identified in Table 3.3-10 are located:in a harsh environment and included in the McGuire NUREG-0588 4 submittal except the containment pressure transmitters, the RWST level transmitters, steamline pressure transmitters, unit vent radiation monitors,

- and the steam relief radiation monitors. The containmer.t pressure transmitters, RWST level transmitters, steamline pressure transmitters and the unit vent radiation monitors are located in mild environments, and therefore, not subject to the requirements of 10CFR50.49. The steam relief readiation monitors are located in a harsh environment; however, the monitors are .not required to

- function for the event that causes the harsh environment. Furthermore, these radiation monitors are not employed as a post-accident parameter for operator

action.

It should also be noted that consistent with NUREG-0737, Supplement 1 and NRC Generic Letter 82-23 Duke Power Company has provided information to the NRC. Staff regarding Regulation Guide ~ l.97, Revision 2. Additional qualifica-

> tion activities (if any) in this area will be persued upon completion of the NRC Staff's review and subsequent issuance of an SER on this subject.

l' i

l- ~ 3 6

[

l r

?

i-

~

we< , -.- + .~..,m,y,.-- , , . , - , , - - . - - , - - .,.. , -,,y. ,,.,m- ,,-,..,,e-,, -,...r--,,,,- ,,,y,- _,%,----w. ,,,.,,-,,74--..,--.py,------<-,,,.%-, ,-m w -

w 1 I

MCGUIRE NUCLEAR STATION - UNITS 1 AND 2 RESOLUTION OF NRC/FRC TECHNICAL EVALUATION REPORT ITEMS The attached information provides the resolutions for items identified iin the-NRC/FRC Technical Evaluation Report (TER) for McGuire Nuclear Station.

Attachment 1 is a table that identifies the TER Items and provides a reference to the appropriate resolution. Attachment 2 provides a discussion of the resolutions for each category with additional detail on certain items .for

-clarification purposes or as requested by the Staff. Attachment 3 provides

. justification for interim operation (JIO) for'the TER items still pending completion of. qualification. It should be noted that although the TER

. references McGuire Unit 1, the equipment covered by the TER and the associated resolutions apply equally to McGuire Unit 2 unless specifically stated other-wise. The resolutions provided herein are consistent with those discussed with the NRC Staff on March 29, 1983.

In addition to the attached infomation which addresses specific equipment items, the following paragraphs address specific issues contained in Section 4.3 of the TER.

TER Paragraph 4.3.3.3 - Nuclear Radiation Dose With regard to radiation dose, the McGuire NUREG 0588 submittal identifies certain equipment as being exposed to a total radiation dose less than the NRC Staff's screening value of 4X10/ Rads. In Duke's response to the NRC's previous Equipment Qualification SER for McGuire, we stated that the equipment which has a 40 year normal dose plus accident dose less than the NRC Staff's screening value is only required for a short term function and is therefore not exposed to a high radiation dose prior to performing its safety function.

Additionally, to support the radiation values identified in the McGuire NUREG 0588 submittal, Duke Power Company has provided to the NRC Staff a radiation analysis including bases, assumptions, and sample dose calculations (Ref.

Duke Power Company letters from H. B. Tucker to H. R. Denton dated February 14 and March 21,1983).

TER Paragraph 4.3.E - Submergence With regard to submergence, Duke's response to the NRC's previous SER states that in a review of the safety-related motor operated valves located below the maximum post-LOCA water level, it was determined that for all defined events the valve motor operators will perform their safety function prior to becoming -

submerged. The flood level will reach the lower most safety-related valves at approximately 5 minutes into an accident situation. These valves, however, will have moved to their safety position at approximately 15 seconds into an accident situation and are not required to reposition subsequent to submergence. This time interval provides adequate margin to assure the completion of the required safety function. Additional information concerning these valves is found in the McGuire FSAR, Section 15.4.1.3.

With specific regard to the TER item concerning failure modes associated with the submerged valves and the effects on other equipment and the operators, we are providing the following additional information:

L-

?. .

' All motor operated valves located below the maximum LOCA water level are categorized as to their operation in relation to flooding. These three cate-

.gories are:

1. The Lyalve is not required.for' post-LOCA operation of any of the safeguard systems. Therefore, operation subsequent to flooding is unnecessary.

2'. The valve is normally in the post-LOCA position. Therefore, it is.not required to reposition before or after flooding.

3. The valve receives a safety signal to close upon the occurrence of a LOCA and is not required to reposition subsequent to flooding.

Duke's response to the previous SER specifically addresses Category 3 above.

However, for all valves in the above categories there is no failure mechanism associated with submergence that could cause these valves to spuriously

. reposition or fail in a position other than the designated safety position.

Additionally there is no failure mechanism associated with submergence that can affect the performance of a safety function by another piece of safety-related_equirment.

With regard to misleading information being supplied to the operator, we have

-determined that there is a . potential for losing control room position indication for these submerged valves due to shorting in the valve limit switch compart-ment. Although these valves are.in their safety position prior to submergence and are not required to reposition following submergence, Duke has implemented an operator aid computer (0AC) application that will produce a valve position report whenever a high water level is detected in the containment sump. This 0AC application is designed to report the position of these valves prior to submergence thereby providing the control room operators with an alternate method of verifying the position of these valves.

g = '

e. ... .-

fc

~

e

(

A-e k

/

si s

ATTACHMENT 1-

'MCGUIRE NUCLEAR STATION - UNITS 1 AND 2 s

-RESOLUTION OF NRC/FRC TECHNICAL EVALUATION REPORT ITEMS IDENTIFICATION OF TER ITEMS AND CORRESPONDING RESOLUTIONS t

.t_

j.

s l~. V- .

>}

I .,

. k.

4 g oe .

n n o u ...ci.c .

Page 'l cf 9

'MCGUIRE NUCLEAR STATION - UNITS 1.AND_2 ,.4 CESOLUTION OF NRC/FRC TECHNICAL EVALUATIQN REPORT-ITEMS' TER .

TER-ITEM COMPONENT- MFGR~ MODEL CATEGORY RESOLUTION 1 Solenoid Valve Valcor V526 II.C 4 2- Solenoid Valve Valcor V526 II.C ~4 3 Solenoid Valve Valcor V70900213 II.A 5,JIO 4' Solenoid Valve Valcor V70900213/V70900211 II.A 5,JIO-5 Solenoid Valve Valcor V70900213 II..A 5,JIO 6 Solenoid Valve .Valcor V526/V573 II.C 4 7 Solenoid Valve Valcor V70900211/V70900213 II.A 5,JIO 8 Solenoid Valve Powers Regulator 2650002 I.B 7

9 Solenoid Valve ASCO NP8316E34E/NP8316E36E II.C 4 10 Solenoid Valve ASCO NP8316E34E II.C 4 11 Solenoid Valve ASCO NP8316E34E II.C 4 12 Solenoid Valve ASCO NP8316E34E/NP8316E36E II.C 4 -

1 13 Solenoid Valve Atwood-Morrill MSIV III.B -3 14 Solenoid Valve Target Rock 77CC- II.C 4 15 Solenoid Valve Borg-Warner FWIV IV 7 16 Valve Motor Operator Rotork NA1/NA2 I.A 1

17 Damper Motor Operator Rotork llNAZ1 I.A 1 18 Valve Motor Operator Limitorque SMB II.A 5

~..

- MdGUIRE NUCLEAR STATION - U' NITS 1 AND 2: Page 2 of 9-

' RESOLUTION OF NRC/FRC-TECHNICAL EVALUATION REPORT ITEMS ITEM COMPONENT MFGR 'MODEL CATEGORY RESOLUTION-I.A

~

19 Valve Motor 0perator Rotork NAl 1 20_ Damper Motor Operator Rotork- 7A/3MW II.C -4

~21 Valve Motor Operator Limitorque SMB II.A 5 22 Valve' Motor Operator Limitorque SMB 'II . A - 5-23 Valve Motor Operator Rotork NA2 II.C 4 i 24 Valve Motor' Operator Rotork NAl I.A 1 25 Valve Motor Operator Limitorque SMB II.A' 5 26 Valve Motor Operator Limitorque 'SMB II.A 5 f 27 Valve Motor Operator Rotork NA2 II.B 6 28 Valve Motor Operator Rotork NAl I.A 1 l 29 Flow Transmitter Veri trak - 59DP III.A' 2 30 Cable Anaconda EP/HYPALON I.A 1 31 Level Switch Robertshaw SL402843 I.B 7,JIO

~

l 32 Level Transmitter Barton 386A II.A 5 33 Level Transmitter (Unit 1) Barton 764 (Lot 2) IV 7 34 Level Transmitter (Unit 1) Barton 764(Lot 2) IV 7 35 Cable Anaconda' EP/HYPALON I.A 1 l

36 Cable Brand-Rex PVC IV 7 i

37 Cable Brand-Rex PVC IV 7 38 Pressure Transmitter (Unit 1) Barton 763(Lot 2) IV 7 39 Pressure Transmitter Rosenount il53GA9 II.B 6

.s +

MCGUIRE NUCLEAR. STATION' . UNITS'l.'ND A b, Page;3 f '9 -

TER RESOLUTION '0F NRC/fi!O TECHNICAL EVALUATION REPORT' ITEMS ' _

.' TER . .

ITEM COMPONENT- i:ECF -MODEL CATEGORY RESOLUTION-

~40 Cable , Brand-Rex XLPE II.A 5 ;.

41 Pressure Transmitter (Unit 1) Barton 763 (Lot 2) IV 7 42 D/P. Switch Solon 7PS1ADW II.A 5 43 D/P Switch .Solon 7PSIADW I.B 7 44 D/P Switch . Solon 7PSIDW- I.B 7 i

45 Signal Transmitter RIS SCl302 IV. 7 46 Acoustical Monitor TEC 1414 I.B 7 l 47 Level System Westinghouse RVLIS I .B. 7,JIO i 48 Radiation Monitor GA RD23 II.A 5 i

49 Cable Rockbestos RSS6104-1081 I.B 7 I~

50 Limit Switch NAMC0 EA-180 II.C 4 i

j 51 Limit Switch NAMC0 EA-180 II.C 4 52 Limit Switch NAMC0 EA-180 II.C 4 53 Limit Switch NAMC0 EA-740 II.C 4 l

j 54 Lirait Switch NAMC0 EA-740 II.C- 4 j 55 Limit Switch NAMCO EA-740 II.C 4 l 56 Limit Switch NAMCO EA-740 II.C 4 57 Limit Switch Micro Switch LSM4N II.A 5

} Se Limit Switch Micro Switch LSM4N II.A 5 l 59 Limit Switch NAMC0 EA170302 II.C 4 3

i 60 Limit Switch NAMC0 EA170302 II.A 5 l

I _

t-MCGUIRE NUCLEAR.-STATION --UNITS:l'AND 2:

' Page. 4 of 9 l RESOLUTION OF NRC/FRC TECHNICAL EVALUATION REPORTilTEMS '

'TER'

TER '-

ITEM - COMDONENT - .MFGR- MODEL CATEGORY- 'REsniUTION 61 Temperature Controller Love Controls. 54L I.B. 7-62 . Temperature Controller *

-Love Controls' 834. I.B 7 63 Temperature Controller Love Controls- 836- ~I.B 7 64 ' Temperature Controller Love. Controls 8134 I .B_ 7-65 . Temperature Controller . Love' Controls 8160 'I.B 7 66 . Temperature Controller Love Controls 8165 - I .B 7.

67 Temperature Controller Love Controls 8173 I.B 68 Temperature Controller Love Controls 8174. I.B 7 69 Thermostat United Electric 800G6CS I .B . 7-70 RTD Weed 101AZNA3C621 I.B: 7 71 RTD Rosemount 176KS- I.B 7, 72 RTD; Rosemount 176KF I.B 7, 73 Motor (NI Pmp) Westinghouse 73F69618 II.C 4 74 Motor (CCP) Westinghouse 72F44587 II.C 4 75- Motor (NS Pmp) Westinghouse 73F56019 II.C 4 ,

76 Motor (RHRPmp) Westinghouse 71F13494 II.C 4 !

77 Motor (SmpPmp) Allis-Chalmers 151335645023 II.A 5,JIO 78 Motor (Ann Vent Fan) Reliance 2YF273608 II.C 4 79 Motor (ABFXF) Reliance- lYF882 I.A 1 80 Motor (DG Vent Fan) Reliance lYF272608 II.C 4

MCGUIRENUCLEARSTATION'-UNITS [l'AND.2-Page 5 cf 9 - ,

TER RESOLUTION OF NRC/FRC TECHNICAL EVALUATION REPORT ITEMS .TER- .

ITEM COMPONENT MFGR- MODEL CATEGORY RESOLUTION 81 Motor (FPCP AHU) Reliance 2YF882311/1YF882311 I.A 1 82 Motor (FPCP) Westinghouse 72F44649 II.C 4 83 Motor (FPCP AHU) Reliance 882311 'II.A 5 84 Motor (GWSmpPmp) Reliance 2Y273734 IV 7.

85 Motor (CCW Pmp) tiestinghouse 72F44689 II.C 4 86 Motor (CC Pmp) Westinghouse 72F44587 II.C 4 87' Motor (NSW Pmp) Westinghouse 72F36530 II.C 4 88 Motor (H2SkimmerFan) Reliance lYF882315 II.A 5 89 Motor (Cont. Air Ret.) Reliance 2XF-330081 II.A 5 90 Terminal Block States ZWM IV 7 91 Terminal Block States ZWM II.A 5 92 Terminal B' lock Buchanan SS & TS II.C 4 93 Terminal Block Stanwick SLS 1.A 1 94 Terminal Block Stanwick SLS II.C 4 95 Terminal Block Stanwick DG II.C- 4 96 Terminal Block Buchanan P0721 I.B 7 97 Terminal Block Buchanan 0721 I.B 7 98 Fuse Littel Fuse Normal & Slo Blo IV 7 99 Fuse Littel Fuse Slo Blo IV 7 100 Fuse' Bussmann FNA IV 7

MCGUIRE NUCLEAR.' STATION - UNITS'l AND'2;,, l Pag 2 6'o f'9 :

RESOLUTION 0F NRC/FRC_ TECHNICAL EVALUATION REPORT. ITEMS <

TER >

TER~

ITEM. COMPONENT MFGR MODEL CATEGORY' RESOLUTION 101 Fuse Bussmann FNA- IV 7-102 Fuse _ Bussmann KTK IV 7 103 Indicating Light Cutler-Hamdr E29' II.A- 5; -

! 104 . Indicating Light Cutlet-Hammer E30 'II.A 5'

. 105 Indicating Light Cutler-Hammer ' E30 IV 7 106 Indicating Light Cutler-Hammer E29 IV 7 107 Selector Switch Cutler-Hammer 10250T- IV 7.

a l 108 e Electrical Switch Cutler-Hammer 10250T. II.A .7

, 109 Fuse Block Bussmann 4575 II.A 5 Fuse Block l 110 Bussmann 3792 II.A 5 111 Fuse B'ack Bussmann

3839 II.A 5

, 112 Fuse Block Bussmann 4439 II.A' 5

113 Fuse Block Bussmann 3792- I.A 'l

{ 114 Fuse Block Bussmann 4575 I.A 1 115 Fuse Block Bussmann. 2808 II.A 5 i 116 Fuse Block Bussmann 2807 II.A 5 i

Relay Cutler-Hammer IV 117 D23 7 i

118 Relay Cutler-Hammer D23 II.A 5 i

j 119 Relay ' Cutler-Hammer D26 II.A 5 I

1

~

MCGUIRE NUCLEAR-STATION - UNITS 1?AND 21 Page .7 cf '9 ;

RESOLUTION OF NRC/FRC TECHNICAL EVALUATION REPORT ITEMS

'. T ER TER' ITEM COMPONENTS MFGR MODEL' CATEGORY RESOLUTION 120 Relay Struthers-Dunn .219 IV' E7 121 Relay Agastat 7000 series ' . IV- 7-122 . Surge Suppressor- Gen. Semi'c' tor Transzorb IV 7 123 Surge Suppressor Gen. Semi'c' tor Transzorb . IV 7 124 Panel (AVFUCnt) Farr -

I.B 7 125 Transformer Westinghouse PRM75 I.A 1 126 MCC Gould K Line I.A 1 127 MCC Nelson Elect. Class 1035u II.A 5 h 128 Alarm RIS ET1215 III.B 3 129 Optical Isolator 1750127 1750127 III.B ,

3 130 Resistor Ohmite Brown Devil IV 7 4 131 Resistor Ohmite Dividohm III.B 3 t-132 Sealant 3M Scotch Cast 9 I.A 1 133 Splice Material Raychem WCSFN II.C 4 134 H2 Recombiner W Sturtevant A I.A 1 135 Elect. Penetration D. G. O'Brien Types A-H, J-M I.A 1 136 Cable BIW XLPE II.A 5 137 Cable Samuel Moore EP/Hyp II.A 5 138 Cable Samuel Moore .EP/Hyp II.A 5 139 Cable Samuel Moore EP/Hyp- II.A 5 i

MCGUIRE NUCLEAR STATION -: UNITS 1 AND 2-

~

Page 8 of- 9 RESOLUTION OF NRC/FRC TECHNICAL EVALUATION REPORT ITEMS '

TER-ITEM COMPONENTS MFGR MODEL CATEGORY RESOLUTION 140- Cable Samuel Moore EP/Hyp II.A :5 141 Cable Samuel-Moore PVC- IV 7-142 Cable Samuel Moore PVC IV 7 143 Cable Okonite Tefzel 280 II.A 5 144 Cable Okonite Tefzel 280 - II.A 5 145 Cable Okonite Tefzel 280 II.A 5 146 Cable Okonite EP II.A 5 147 Cable Okonite EP II.A 5 148 Cable Okonite EP II.A 5 149 Cable Okonite EP II.A 5 150 Cable Okonite EP/Hyp II.A 5 151 Cable Okonite Hypalon I:.A 5 152 Cable Okonite Hypalon II.A 5 153 Cable Brand-Rex XLPE II.A 5 154 Cable Brand-Rex XLPE II.A 5 155 Cable Brand-Rex XLPE II.A 5 156 Cable Anaconda EP/Hyp I.A 1 157 Cable Anaconda EP/Hyp I.A 1 158 Power Supply Lambda LCS IV 7 159 Valve Motor Operator Rotork NA2 II.C 4 Reliance lYF882311 II.A 5 l 160 Motor (FPAHU)

k MCGUIRE NUCLEAR STATION - UNITS 1 AND 2.. -

Page 9 5f 9 r,

. RESOLUTION'0F NR'C/FRC TECHNICAL-EVALUATION REPORT ITEMS TER TER--

ITEM COMPONENTS MFGR MODEL CATEGORY s RESOLUTION -

161~ Panel':(ABFU Cnt) Allison .

.I.B. -7 A

i e

i i

- =

-4 . -

3 3 I Kf! _ - .. g t u

=

S

y>

L 4

I w

1 ATTACHMENT 2 9

a MCGUIRE NUCLEAR STATION - UNITS 1 AND 2

.. RESOLUTION OF NRC/FRC. TECHNICAL ~ EVALUATION' REPORT ITEMS 1

R'ESOLUTION DISCUSSION a

, r s

6 T'h .*

i

.f -

i

+

' w:

1 4 -

g .-

.. S :- c.fW 4 Attachment 2 g Page 1 of 9 MCGUIRE NUCLEAR STATION - UNITS 1 AND 2 L -

~ RESOLUTION 0F NRC/FRC TECHNICAL = EVALUATION REPORT ITEMS Resolution No. Resolution Discussion 1, :This equipment is in TER. Category I.A,7E quipment Qualified. No o ,

, resolution.is required for this equipment.

2. This equipment is in: TER Category,III.A,' Equipment Exempt from Qualification. No resolution is required for this equipment.

"3. This' equipment is in TER Category III.B. Equipment Not in the Scope

? of the Review. No resolution is required for this equipment. It

should be 'noted that TER Item 13 (solenoid valve supplied by Atwood-

~

Morrill as a part of the main steam isolation valves) was incorrectly identified as.a TER Category III.B item. .The environmental quali-

/

fication of these solenoid valves is documented in Atwood-Morrill Report:201-39500 dated May 1, 1979.

g. . ,

4 '", 1 4.x _ This equipment is in TER Category II.C, Equipment Satisfies All

. Requirements Except Qualified Life or Replacement . Schedule. Justified.

Duke Power Company has. reviewed the items in this category and.

determined that the TER concerns can be satisfactorily resolved.for

+

jMcGuire. . Documentation of the specific resolutions for each TER.

Item is currently in progress. As discussed with the NRC Staff on T -March 29, 1983, the methods for resolving these concerns are-

' ' - consistent with the NUREG 0588 Category II requirements and NRC

- Generic Letter 82-09 and include one or more of the following:

e ' Aging simulations were included in the test program for the equip-

' ment. A qualified life based.on-McGuire conditions has been n determined with appropriate equipment / component replacement schedules

. established.

i- . 9 Surveillance and maintenance activities established to review equip-ment for significant' aging degradation.

t 0 Equipment has been determined to have no significant aging mechanisms

3, based on material evaluation or Duke experience. In all cases where p 1 radiation .is an_ environmental parameter, the equipment has been shown

'~ '

to be qualified for the 40 year normal dose plus the appropriate g; accident; dose (typically 1 year).

. With specific regard to TER Items 55 and 56 (EA-740 limit switches furnished by NAMCO), it should.be noted that these two items are not

- used in safety-related applications outside containment and there-m fore do not require environmental qualification.

F T 5. This equipment is in TER-Category II.'A, Equipment Qualification Not

~

Established. . Duke Power Company has reviewed the items in this category. 'Ter.hnical resolutions have been determined and documen-tation of the specific resolutions for each TER Item is currently in

. progress. Additionally, key resolutions discussed with the NRC Staff on March 29, 1983 are.as follows:

. /

4 P-L

V H Page 2 of 9 g ,

p '

- Resolution No. Resolution Discussion O Traceability of installed equipment to the qualification-documentation

!% - was a principle concern. for. cables (TER Items 40, 136-140, and 143-

. 155),' Limitorque valve motors (TER Items 18, 21, 22,-25, and 26),

2:

. hydrogen skinmer. fan motors (TER Item 89). For these items, Duke

~ Power Company has identified the auditable link between the installed equipment and the qualification documentation and is updating the

-qualification files with this information.

I This effort will be based on manufacturer's certifications that are 2 traceable through specifications, purchase orders, or other pertinent

, documents..

0 Valcor solenoid valves models.V70900211 a'nd V70900213 (TER Items 3, 4, 5, and 7) were originally qualified by similarity to another Valcor solenoid valve. However, the specific models identified above are

presently. undergoing qualification testing that is scheduled for completion in September 1983. Duke Power Company intends to use the qualification test results from this new test program as the basis of qualification for these Valcor solenoid valves.

Re'fer to the attached JIO for this equipment.

O ;Solon differential pressure switches model 7PSl ADW (TER Item 42),

L located in the upper _ containment are qualified for less than one

hour. .These switches detect.high differential pressure between the upper and lower containment associated with large breaks and actuate to provide an open permissive to dampers located between

, the: upper and lower containment. This high differential pressure in containment will. occur and equalize less than one minute into the event. .Once the switches have provided the permissive. signal, they

-are electrically isolated from the circuit and perform no further safety function. Based on the desi of. the switches (upper containment)gn ,- anddescribed above, the need for theirthe location function

!- 'only for a large break event, qualification for less than one hour.

-is justified. Additionally, margin is provided between the required time (1 minute) and the qualified time (5 minutes).

0 . Micro Switch limit switches model LSM4N (TER Items 57 and 58)

~ provide damper position indication only and are used to observe damper position during testing of the associated ventilation system.

.These switches perform no safety function, are not used by the-l operators as a basis for a required action and their failure cannot i

= prevent satisfactory accomplishment of any required safety function.

Additionally, these switches will be removed from safety power prior r

to startup following the first refueling outage of the respective McGuire units.

E 8 . Allis Chalmers sump pump motors model 151335645023 (TER Item 77)

L located outside the containment are exposed .to only a post-LOCA L . radiation environment. Duke Power Company has pursued the radiation qualification of these motors with the manufacturer and obtained a jf . manufacturer's statement that the motor is qualified. 'However, Duke i - Power Company will replace these motors with qualified motors having

. complete qualication documentation.

L i

c -

m Page 3 of 9 g

Resolution No. Resolution Discussion Refer to attached JIO for this equipment.

6. This equipment is in TER Category II.8, Equipment Not Qualified.

Duke Power Company has reviewed the two items in this category.

Based on our review we have determined that the following additional information addresses the TER concerns and in conjunction with the qualification documentation referenced in the McGuire NUREG 0588 submittal demonstrates qualification of the two equipment items.

8 TER Item 27 - Rotork Model NA-2 Valve Actuators Located Outside Containment Statement of Problem: Following exposure to 212 F steam environment for.200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months , the torque switch mechanism'in the Rotork NA-2 style actuator failed resulting in the motor running to stall and burning up following the actuation of a valve in the close direction. This situation is described in Rotork Test Report TR-3025.

Background Information: The torque swi.tch mechanism of the NA-2 actuator was the component which failed during qualification testing as reported in'TR-3025. The NA-2 torque switch mechanism (helix)is made of a thermoplastic material, nilotron, which at approximately 180"F becomes pliable resulting in failure to actuate the torque switch at the end of valve stroke. As noted in our response to the

' McGuire Unit i equipment qualification SER, TR-3025 demonstrates that at least one valve operation is available after a torque switch

mechanism failure; therefore, the valves are capable of moving to their safety position. It should be emphasized that the tor';ue ,

switch failure could occur only after the valve has reacheo its safety position and would not affect the valves' ability to remain in its safety position, would not affect other safety-related equipment, and would not mislead the operator.

Duke has analyzed all NA-2 actuator applications at McGuire and has determined that once the actuator has reached its safety position, no additional safety operation is required.

Conclusion:

Based on the Rotork NA-2 test report TR-3025'and the above discussion, Duke has determined that these actuators are capable of performing their safety function and that continued use of the NA-2 actuator in its current applications is acceptable.

8 TER Item 39 - Rosemount Transmitters Model 11536A9 (RCS Wide Range Pressure Transmitter) Located in the Annulus.

Statement of Problem: Based on the FRC review, the Rosemount ll53GA9 transmitter is identified as not qualified for accident conditions. This conclusion was reached based on the Rosemount qualification report submitted as part of the H. B. Robinson facility SER response. This H. B. Robinson report identifies a failure of some components in the 1153 Series A transmitters due to environmental testing in accordance with IEEE 323-1974 which significantly exceeds the McGuire requirements.

g.. .

Page 4 of 9 9

s 4 Resolution No. Resolution Discussion

, t . Background Information: The applicable qualification document for .

the McGuire ll53GA9 transmitter, as referenced in_ Duke's NUREG 0588 submittal, is:Rosemount Report No. 3788, Revision A. This report 4 - l documents results 'of type testing which qualifies the Model 1153 Series ~ A transmitter for Class lE service in Nuclear Power Generating

, : Stations in accordance with.IEEE 323-1971. Specifically, Rosemount Report'No. 3788, Revision A' documents that the Rosemount Model 1153 -

- Series A transmitter successfulTy completed testing with no signifi-i-

cant anomalies under the following conditions: Temperature-350*F ;7 Pressure-120_ psig;-relative humidity-100%; and radiation dose-4X10 R; t and chemical spray. The accident environment for the McGuire Unit 1 and 2 RCS wide-range ~ pressure. transmitters, located in the annulus,

is 142*F, relative humidity 100% and radiatica dose 1.2X107R.

Pressure,, steam, and chemical spray environments are not applicable environmental parameters ;in the annulus. With regard to transmitters LO-ring seal ~ integrity,' station procedures will require 0-ring seal replacement consistent with transmitters calibration intervals.

Replacement intervals for the entire transmitter or the circuit board 4 is.being reviewed and will be addressed and included in our qualifi-cation flies.-

Conclusion': The'Rosemount report referenced in the H. B. Robinson

~

SER response;does not apply to the Duke transmitters since the-

' report addresses a qualification program which significantly exceeds the licGuire requirements. Therefore, based on Rosemount's Report .

No. 3788,- Revision A and the above discussion, Duke has determined-that the subject transmitters are qualified to perform their safety function in the annulus accident environment as identified in the

'McGuire NUREG 0588 response.

o

77. This. equipment is in either TER Category I.B . Equipment Qualifica-_- ,

tion Pending Modification or TER Category IV, Documentation Not Made ,

'Available. -Duke _ Power Company.has reviewed the itens in these two categories and determined that the major deficiency noted in each - ,

category is documentation not 'available for review (Note:

circumstances related to documentation not available for review J . included qualification testing _ not complete at the time of our submittal, prcprietary nature of certain qualification documentation, and certain documents not requested by NRC/FRC). tWe have further determined that qualification documentation is now available in Duke files'for the equipment' items noted in the following table.

For the remaining equipment-items in these two categories, the

- following information is provided:

0 . TER Item 31; Robertshaw Level Switches"- Model- SL402843 These. level switches are installed.outside containment in the dog-r- -house and function .to terminate main feedwater flow in the event of a main feedwater line break in the doghouse. Main feedwatsr termin-

' - ation is required in order to prevent the flooding of safety-related equipment in the doghouse.

6 i -

evN ,.w, w e -ryw,s- .,,wew~-- .,-r-wwwve=r- e ew,-,yvn-,---c--e , e + ew w ww=-- w e*w,.y.- #-e PmWw'*="~ew" ' - ' - * " -

v-o . .. c

.lNy .

. i >

r ' Paga 5 of 9 4

i )

j

~ Resolution No.- -Resolution Discussion f As: stated in the Duke NUREG-0588 submittal for McGuire, these

switches were in a qualification program that was scheduled for completion in 1982. - Following evaluation of the results of the themal aging portion of this qualification program. Duke has-decided to replace the Robertshaw level switch withia Magnetrol level switch which is presently undergoing qualifica->

tion testing. :The testing is scheduled for completion b y April

.1983. .The results of the Magnetrol level switch testing will be '

provided,in the McGuire NUREG-0588 submittal.

s Refer- to the attached.J10 for the Magnetrollevel switches. 3 4- TER' Item 47 - Reactor Vesse(Level Instrument System (RVI.IS) 4

The RVLIS .isia TMI/NUREG-9737 item (II.F.2). The environmental .,

j qualification documentation' for the equipment in this system 1. .

o subject to harsh environment is scheduled to be available by May 31, 1983. , ..,

I +

-Refer to the at$ ached-J10~ for the RVi.IS. a g

8 TER Item 71; Rosemount RTD's - Modekl N6KS' These RTD's are provided to monitor reactor coolant. system wide

!.. . range temperature and-are used for post-accident monitoring indication supplemental documentation to MCAP-9157 has established a 10 year qualified life for the Rosemount Model 176KS RTD's n ,

j a The applicable equipment summary sheet has been revised to reflect , .

7 this supolemental documentation (Attachment 1, Page 10). ,

9 TER Item 72; Rosemount rid's.- Model.176KF .?

These RTD's 'are. provided to monitor reactor coolant system' narrow- q range temperature and have a short term reactor trip input func-tion. As stated in the McGuire NUREG-0588 submittal, these RTD's "

o :would'he' replaced on a 10 year cycle unless it could be shoutithat EPR-is a.non-critical material of the RTD. Based on our review of /

the materials used in the RTD, we have found that'EPR whichAaf ,e initially thought to be a material in these RTD's is ,in fact not -

an RTD material. Therefore, based on the qualification' report for these RTD's, a review of the materials of these RTD.'s-(including thermal and radiation aging),_and the application of these these RTD'_s are qualified for 40 years of normal operation,RTD's, plus their. short-term trip function. *'

s l

.v n' ,

+N 6 e

/

y

( -

l'

,. / d wa ~. . _ . - . _ _ _ . _ . _ . _

__ f J

Page 6 of 9 Resolution No. Resolution Discussion 8 TER Item 84; Reliance Motor - Model 2Y273734 This motor is installed outside containment and serves as the motor drive for the groundwater drainage sump pump. Although this motor

-_is exposed to a pipe break environment, it is not required to function for any pipe break event. Further, failure of this motor-

'c ,

following exposure to the postulated harsh environment will not prevent the satisfactory accomplishment of any required safety function by other safety-related equipment.

a e TER Item 124 - Annulus Ventilation Filter Unit Control Panels

. These panels have been relocated to a mild environment on both

. McGuire units.

., 11 0 TER Item 161 - Auxiliary Building Filter Unit Control Panel

"#- These panels have been modified and reclassified as non-safety-related on both McGuire units; therefore, environmental _ qualification is not required. .

2 5,

3r .

(c; 4-

~ '

,g.

98-

"t ry.4 h

'e 5 k '.

.. , m ...,, __ ,

Attachment 2 Pag 2 7'cf 9 MCGUIRE NUCLEAR' STATION - UNITS 1 AND 2 -

RESOLUTION 0F.NRC/FRC TECHNICAL EVALUATION REPORT ITEM '4 QUALIFICATION DOCUMENTATION REFERENCES FCR CATEGORY I.B AND'IV ITEMS FRC ITEM NO. COMP 0NENT MFGR MODEL # OUALIFICATION DOCUMENTATION

'8 Solenoid Valve Powers Regulator 2650002 CCL Test Report A-490-82 15 . Solenoid Valve Borg-Warner FWIV Borg Warner Test Reports 1785 and 1779, dated ll/12/79 33 Level Transmitter (. Unit 1) Barton 764 (Lot 2) WCAP-9885 34 Level Transmitter. (Unit 1) Barton 764 (Lot 2) WCAP-9885

35 Cable Brand-Rex PVC Duke Report QTF TR-032 (Supersedes TR-017)

, 37 Cable Brand-Rex PVC Duke Report QTF TR-032 (Supersedes TR-017) 38 Pressure Transmitter (Unit 1) Barton 763 (Lot 2) WCAP-9885 41 Pressure Transmitter (Unit 1) Barton 763 (Lot 2) WCAP-9885 43 D/P Switch Solon 7PSIADW CCL Report A-490-82 ,

44 D/P Switch Solon 7PSIDW CCL Report A-490-82

45 Signal Transmitter RIS SC1302 RIS fianual SC-1302 (MCM-1346.00-0010) 46 Acoustical TEC 1413 TEC Test Report 517-TR-03,

. Rev. 3 i

l 49 Cable Rockbestos RSS6104-1081 Rockbestos Test Report 2806

m

~

Attachment 2 Page 8 of 9

.MCGUIRE NUCLEAR STATION .

FRC ITEM NO. COMPONENT MFGR MODEL # OUALIFICATION DOCUMENTATION 61 Temperature Controller Love Controls 54 CLL' Test Report A-490-82 62 Temperature . Controller Love Controls 834 .CCL Test Report A-490-82 63 Temperature Controller Love Controls 836 CCL Test Report A-490-82 64 Temperature Controller Love Controls 8134 CCL Test Report A-490-82 65 Temperature Controller Love Controls 8160 CCL Test Report A-490-82 66 Temperature Controller Love Controls 8187' CCL Test Report A-490-82 67 Temperature Controller Love Controls 8173 CCL Test Report A-490-82 68 Temperature Controller Love Controls 8174 CCL Test Report A-490-82 69 Thermostat United Electric 800G6CS CCL Test Report A-490-82 70 RTD Weed 101AZNA3C621 CCL Test Report A-490-82 90 Terminal Block States ZWM ESSEM IV-B-4 & IV-B-5/ Duke Analysis 96 Terminal Block Buchanan P0721 CCL Test Report A-490-82 97 Terminal Block Buchanan 0721 CCL Test Report A-490-82 98 Fuse Littel Fuse Normal & Slo Blo ESSEM III-A-7/Derating Curve 99 Fuse Littel Fuse Slo Blo ESSEM III-A-7/QTF TR-047 100 Fuse Bussmann FNA ESSEM III-A-4/QTF TR-040 101 Fuse Bussmann FNA ESSEM III-A-4/Derating Curve 102 Fuse Bussmann KTK ESSEM III-A-1/Derating Curve _

105 Indicating Light Cutler-Hammer E30 ESSEM VI-C-1/QTF TR-040

-W

Attachment t

' Page 9 cf 9 ,

MCGUIRE NUCLEAR STATION FRC .

l1 ITEM NO. COMPONENT MFGR- MODEL # QUALIFICATION DOCUMENTATION 106 Indicating Light - Cutler-Hammer E29 -ESSEM III-B-1/QTF T -040 107 Selector Switch Cutler-Hammer 10250T ESSEM VI-A-1/QTF TR-040 117 Relay Cutler-Hammer D23 ESSEM.VII-A-2,l/QTF TR-040 120 Relay Struthers-Dunn ,

219 ESSEM VII-A-3/ Duke Test Report 121 Relay Agastat 7000 series ESSEM VII-C-5/Agastat Spec.

122 Surge Suppressor Gen. Semi'c' tor Transzorb ESSEM III-C-1/G.S. Spec.

123 Surge Suppressor Gen. Semi'c' tor Transzorb ESSEM III-C-1/G.S. Spec.

130 Resistor Ohmite Brown Devil ESSEM IX-B-2/Derating Curve 141 Cable Samuel Moore PVC Duke Report QTF TR-032 (Supersedes TR-017) 142 Cable Samuel Moore PVC Duke Report QTF TR-032 (Supersedes TR-017)

Power Supply Lambda LCS ESSFM VIII-G-1/ Lambda Spec.

158

g: :q

. (, . -,

f( .. 1

^

Q A

v f

v_

ATTACHMENT 3 4

~

- - MC'GUIRE~ NUCLEAR STATION - UNITS 1 AND'2 RESOL'UTIONOFNRCfFRCTECHNICALEVALUATIONREPORTITEMS

-~ JUSTIFICATIONS FOR INTERIM OPERATION' I

k' I

J O

O

' ' :v_

I, k-

.p #

Attachment 3 MCGUIRE NUCLEAR STATION - UNITS 1 AND 2 JUSTIFICATION FOR INTERIM OPERATION TER' Items 3, 4, 5, & 7 - Valcor Solenoid Valves (Models V70900-21-1, - 3)

- These Valcor solenoid valves have two basic applications at McGuire - system isolation (de-energize upon receipt of a safety signal) and containment hydrogen sampling (periodically energize to open sample lines). Recent qualification program results (Valcor Report QR 70900-21-1 and_3) demonstrate proper qualifi-cation for the system isolation function; however, qualification for longer than 2 days post DBE for the containment hydrogen sampling application has not been demonstrated by the Valcor program. Therefore, this JC0 addresses only the hydrogen sampling application for these solenoid vaive operators.

As originally designed, the sample valves for .the containment hydrogen sampling system were to be normally closed when its associated solenoid was de-energized.-

This design required the system operator to open the sample valves (.i.e.,

energize'the solenoids) to take a containment air sample. However, because of the qualification program results regarding long term operability demonstrated (2 days post DBE) versus the system operability requirement (10 days post DBE),

a system design change is currently being implemented. This design change now makes the sample valves normally open when the solenoid is de-energized, there-by assuring that a containment air sample would be available for at least 10 days post-DBE. It should be noted that-the containment isolation function for .

the hydrogen sample system is performed by other qualified valves.

Duke Power Company is reviewing the Valcor qualification program results to

. determine the action required to extend the post DBE operability of these solenoid operators. - Resolution of this issue is scheduled for March,1985 and may involve solenoid valve modifications or permanent system design changes.

f

~

Attachment 3 MCGUIRE NUCLEAR STATION UNITS 1 AND 2 RESOLUTION OF JUSTIFICATION FOR INTERIM OPERATION TER Item 31 - Robertshaw Level Switm (Model SL402843)

As stated in the McGuire NUREG 0588 submittal, the Robertshaw level switches were in a qualification program that was scheduled for completion in 1982.

Following evaluation of the results of the themal aging portion of this qual-ification program, Duke decided to replace the Robertshaw level switch with a Magnetrol level switch which is presently undergoing qualification testing.

The baseline functional tests, themal and cyclic aging, and seismic portions of the Magnetrol test program are complete with only the HELB simulation remaining to be completed. The HELB. test is scheduled for completion by the end of April, 1983.

Based on our decision to replace the Robertshaw level switches with Magnetrol level switches (Model A103F-3X-Y-MPG-TDM-SlMD4DC-SlMD4DC-S1MD4DC) and since the Magnetrol switches have not yet completed qualification testing, the following justification for interim operation is provided for the Magnetrol switches pending completion of qualification testing.

Magnetrol level switches are not installed on both McGuire units. These switches are located outside containment in the doghouse and function to terminate main feedwater flow in the event of a main feedwater line break in the doghouse. Main feedwater termination is required in order to prevent the flooding of safety-related equipment in the doghouse. The feedwater line break environment in the doghouse results in a temperature of 240*F and a very brief pressure transient to 9psig.

It is our engineering judgement that the Magnetrol level switches will not only successfully pass the HELB portion of the qualification program but are also acceptable for interim ooeration based on testing. Magnetrol has performed dry heat tests on the identical switch mechanisms utilized in the McGuire level switches at 300 F for up to 1954 hours0.0226 days 0.543 hours 0.00323 weeks 7.43497e-4 months with no failures. In addition, elevated temperature and humidity aging tests were performed on a Magnetrol model no.

A153F-Y-MPG-TDM-SlMD4DC-S1MD4DC-SlMD4DC level switch, which is similar to the McGuire switches for a total of 160 hours0.00185 days 0.0444 hours 2.645503e-4 weeks 6.088e-5 months at 300 F and 480 hours0.00556 days 0.133 hours 7.936508e-4 weeks 1.8264e-4 months at 95-100%

relative humidity. The only problems encouraged were 1) a broken housing cover gasket after 110 hours0.00127 days 0.0306 hours 1.818783e-4 weeks 4.1855e-5 months at 300 F, 239 hours0.00277 days 0.0664 hours 3.95172e-4 weeks 9.09395e-5 months at 95-100% relative humidity and 30 to 40 cover installations and 2) micro switch mounting screws were becoming loose during the test. These are not a concern for the McGuire evaluation because

1) the problem with the housing gasket occurred at 110 hours0.00127 days 0.0306 hours 1.818783e-4 weeks 4.1855e-5 months , which greatly exceeds the duration of the postulated McGuire doghouse environment and occurred after at least 30 cover installations. Duke maintenance procedures requires an inspection of the housing gasket each time the cover is removed and 2) Magnetrol now utilizes lock-tite on the micro switch mounting screws to prevent loosening of the screws.

Resolution:

The equipment sumary sheet (Attachment 3, page 30a) has been revised to reflect new documentation (TR-060) which qualifies the Magnetrol level switch to its postulated accident environment.

. .s-l Attachment 3 MCGUIRE NUCLEAR STATION - UNITS 1 AND 2 RESOLUTION OF JUSTIFICATION FOR INTERIM OPERATION

'TER Item 47 - Reactor Vessel Level. Instrument System (RVLIS)

The RVLIS is a TMI/NUREG 0737 item (II.F.2) which is being furnished for McGuire by Westinghouse. This system is installed on Unit 1 and is required by license condition to be installed on Unit 2 prior to startup following the first Unit 2 refueling outage. It should be noted that even though this

. : system is installed on Unit 1, it will not be declared operable until upgraded emergency operating procedures are approved and implemented (late 1983).

The environmental qualification of the equipment in this system subject to a harsh environment is complete and addressed in the McGuire NUREG 0588 submittal with the exception of the Minco strap-on RTD's. Westinghouse has recently'successfully completed the qualification of these RTD's which will be documented in WCAP 8687, Supplement 1, E42A in late May,1983.

However, because Duke Power Company has not reviewed the qualification data and since the Unit 1 RVLIS system will be energized for test purposes prior to being declared operable, we have reviewed the impact of failure of the

.Minco strap-on RTD's on other safety-related equipment. Our review indicates that failure of the Minco RTD's would not prevent the satisfactory accomplishment of any required safety function by other safety-related equipment.

Resolution: Review of the Minco strap-on RTD's qualification report has been completed and qualification of the RTD's is documented in Attachment 1, page 10A.

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

.. - .- * =

Attachment 3 s- MCGUIRE NUCLEAR STATION - UNITS 1 AND 2

- RESOLUTION OF JUSTIFICATION FOR INTERIM OPERATION

'TER Item 77'- Allis Chalmers Pump >stor (Model 151335645023)

These motors are -located outside the containment and subject only to post-LOCA recirculation radiation (9.1x104 Rads TID 40 years plus 1 year post-accident). These motors are provided to drive sump pumps associated with RHR and containment spray pump leakage collection.

' Duke Power Company has obtained a letter from the manufacturer stating that these motors are qualified for the postulated radiation environment. However, s~

we have been unable to obtain copies of test / analysis data to support the manufacturer's statement. - As a result of the lack of confirmatory documentation,

'these motors are being replaced with Reliance Electric motors having complete qualification documentation for the postulated radiation environment. These motors are scheduled for replacement on both McGuire units by May 16, 1983.

Interim operation. until the changeout is. complete is acceptable based on the

extremely low normal radiation dose that would be experienced by these motors

^ prior to'their changeout (by May 16,'1983), accessibility of these motors for maintenance / repair, and the manufacturer's certification of radiation qualifi-

. cation at.1X103 Rads.

Resolution:

Change-out of the Allis Chalmers pump motor to Reliance pump motors is complete and qualification of the Reliance pump motors is documented in

-Attachment 4, Page 7.

i 4

A

-w .c ..r,<,. ..,,-,w-, - ,r->-6,w.,.c..,rm,.-- , --ww.,-v..,,-,.m-,y.-% -, , , , , , - , - ...,.m.wy, m c,

T" :

ATTACHMENT 1

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT LOCATED INSIDE CONTAINMENT Pg Rev. Page Rev. M Rev.

1- 1 - IN1 1 2 1- 1N2 2 "3 1 IN3 1 4 2.

4A 0

.( ; 5 1 6 1 71 :1 8 1 8A 0 9 2 10 2 10A 0 11 1 12 1 13 1 14 1

,15 1 15A 0 16 1 17 'l 18 2 19 1 20 1 21 1 22 1 23 . 1 23A 1 24 1

25 1 26 1 27 1 28 1 29 2 30 1 30A D 31 2 32 1 33 1 34 2 35 2 0 = Deletion

,$p McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 1 ,

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev.~ 1 LOCATED INSIDE CONTAINMENT l

EQUIPMENT ID: Transmitter - Pressurizer MANUFACTURER: Barton MODEL #: 763 (Lot 2)

(1) Pressure (Lower Containment) , (NSSS)

(Unit 1)

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: 380 F SI Initiation 5 minutes +10% Max. Error 7.7%

Press: 14.8 psig Press: 75 psig (<5 min.) post DBE (5 min.)

RH: 100% RH: 100%

Rad: 2.5X108R Rad: SX107R Chem Spray: N/A Chem Spray: Boric-acid and sodium hydroxide soln.

2750 ppm Boron, 8.5 pH QUALIFICATION REPORT: WCAP 9885 (MCM-1399.03-439)

METHOD: Test ECSE

o.

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page'2

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT. Rev. 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Transmitter - Pressurizer MANUFACTURER: Barton MODEL'#: '764 (Lot 2)'

(1) Level (Lower Containment) (NSSS)

(Unit-1)

ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ACCIDENT TO WHICH DEMONSTRATED REQUIRED DEMONSTRATED

. ENVIRONMENT REQUIRED IN i (2) QUALIFIED ACCIDENT (% OF' SPAN) (% OF SPAN)

ENVIRONMENT (3) i Temp: 327*F Temp: 380*F 2 weeks 4 months i 25% Max. Error 15%

Press: 14.8 psig Press: 75 psig post DBE post DBE RH: 100% RH: 100%

Rad: 1.4X107R Rad: SX107R l Chem Spray: Boric Chen Spray: Boric

, acid and sodium acid and sodium tetraborate soln. hydroxide soln.

2750 ppe Boron,

j. 8.5 pH ,

J 4

QUALIFICATION REPORT: WCAP 9885 (MCM-1399.03-439) i METHOD: Test .

i I ECSE i

p 1 ,..

3.

V ;

-s

i j' .

W McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 3 SUMARY OF ENVIRONhENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev.-1

.. LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Transmitter - 5/G Level (NR) MANUFACTURER: Barton MDDEL #: 764 (Lot 2) '

(1) (Lower Containment) (NSSS)

(Unit 1) .

ACCIDENT ENVIRO MENT ~ OPERABILITY OPERABILITY ACCURACY- ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMDNSTRATED REQUIRED . DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)

ENVIROMENT(3)

Temp: 327*F Temp: 380*F Reactor trip 4 months Trip Function: <+5%-(5 min)

Press: 14.8 psig Press: 75 psig (<5 min.) post D8E +5% (5 min)'

RH: 100% RH: 100% Plus 4 months Rad: 2.3X107R Rad: 5X107R post DBE PAM Function: Max Error 15% "

Chem Spray: Boric Chem Spray: Boric i 25% (4 mo) (4 mo) ccid and sodium acid and sodium .

tetraborate soln. hydroxide soln. (Note 5) 2750 ppe Boron, 8.5 pH QUALIFICATION REPORT: WCAP 9885 (MCM-1399.03-439)

METHOD: Test ,

ECSE

y - .7 s

't 1 - ef s

f

^

'c L w

.McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page'4' SUMARY OF.ENVIROMENTAL QUALIFICATION OF CLASS IE EQUIPMENT - -

Rev. 2-LOCATED INSIDE CONTAIMENT EQUIPMENT ID: Transmitter RCS Flow - MANUFACTURER: Veritrak- MODEL #: 590P4 (1) (Lower Containment) (NSSS)

(Unit 1)

ACCIDENT ENVIRONPTNT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT = TO WHICH REQUIRED IN DEMONSTRATED REQUIRED ' DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN).

ENVIRONMENT (3)

^

The RCS flow signals are not required for accidents that cause a change in the normal containment operating environment.

Failure of the RCS flow transmitters due to the adverse environment following an accident will not prejudice the safety function of other equipment claimed in the accident analysis. Additionally, the information provided by this instrument is not employed'as a post-accident monitoring parameter. ,

QUALIFICATION REPORT: N/A METHOD: N/A MPIC

v McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 4A

SUMMARY

.0F ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Transmitter - MANUFACTURER: Veritrak MODEL #: 76DP1 ,

(1) Main Stear Flow (Unit 1)

ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURALY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)

ENVIRONMENT (3) 4 j The Main Steam flow signals are not required for accidents that cause a change in the normal containment operating environment i

) Failure of the Main Steam flow transmitters due to the adverse environment following an accident will not prejudice the safety i function of other equipment claimed in the accident analysis. Additionally, the information provided by this instrument is not employed as a post-accident monitoring parameter. -

1

)

4 QUALIFICATION REPORT: N/A i

i HETH00: N/A i

I MPIC

4 1

McGUIRE NUCLEAR STATION-- UNITS 1 AND'2. 'Page 5 SUMARY.0F ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT - 'Rev. 1:

LOCATED-INSIDE~ CONTAINMENT ,

~

1 EQUIPMENT ID: . Transmitter - Prossurizer . MANUFACTURER: Barton MODEL #: 763'(Lot 4, Lot'5)

(1) . Pressure (Lower Containment) (NSSS)

(Unit 2)

ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY:

ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED i

(2) -QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN) 1 ENVIROMENT(3) :1 1.

Temp: 327*F Temp: 420*F SI Initiation 5 minutes +10% +10%-

14.8 psig Press: 57 psig Press: (<5 min.) post DBE RH: 100% RH: 100%

i Rad: 2.5X108R Rad: SX107R 1 l Chem Spray: N/A Chen Spray: Boric j acid and. sodium

hydroxide soln.

l 2500 ppe Boron, .

-[

j 10.7 pH -

i l

j QUALIFICATION REPORT: WCAP 8587 Supp. 1, EQDP-ESE-1 and WCAP 8687 Supp. 2, E01A

(MCM-1399.03-0472). -

l 1

i METHOD: Test -

1 i

MPIC 1

l -

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 6

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Transmitter - Pressurizer . MANUFACTURER: Barton MODEL #: 764 (Lot 4, Lot 5)

(1) Level (Lower Containment) (NSSS)

(Unit 2)

ACCIDENT ENVIRONMLNT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)

ENVIRONMENT (3) .

Temp: 327*F Teup: 420*F 2 weeks 4 months 125% 115%

Press: 14.8 psig Press: 57 psig . post DBE post DBE RH: 100% RH: 100%

Rad: 2.5X108R Rad: SX107R Chem Spray: Boric Chen Spray: Boric ccid and sodium acid and sodium tetraborate soln. hydroxide soln.

2500 ppm Boron, 10.7 pH QUALIFICATION REPORT: WCAP 8587 Supp. 1, EQDP - ESE-3 and WCAP 8687 Supp. 2, E03A (MCM-1399.03-0472)

METHOD: Test MPIC

I McGUIRE NUCLEAR STATION - UNITS 1.AND 2 1 Page 7 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT - Rev. 1 J LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Transmitter - S/G Level (NR) MANUFACTURER: Barton MODEL #: 764 (Lot 4, Lot 5)

(1) (Lower Containment) (NSSS)- 'l (Unit 2) i 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: 420*F Reactor trip 4 months Trip Function +5% (5 min)-

Press: 14.8 psig Press: 57 psig (<5 Minutes) post DBE +5% (5 Minutes)

RH: 100% RH: 100%

Rrd: 2.3XIO7R Rad: SX107R Plus 4 months PAM Function: 15% (4 months)

Chem Spray: Boric Chem Spray: Boric post DBE 125% (4 months) acid and sodium acid and sodium tetraborate soln. hydroxide soln.

2500 ppa Boron, 10.7 pH l

QUALIFICATION REPORT: WCAP 8587 Supp. 1, EQDP-ESE-3 and WCAP 8687 Supp. 2, E03A (MCM-1399.03-0472)

HETH00: Test MPIC l

4

. McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 8-

SUMMARY

OF ENVIRONME!!TAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev.' 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Transmitter - RCS Flow MANUFACTURER: - Barton MODEL #: 764 (1) (Lower Containment)

(Unit 2)

ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)

ENVIRONMENT (3)

The RCS flow signals are not required for accidents that cause a change in the normal containment operating environment.

Failure of the RCS flow transmitters due to the adverse environment following an accident will not prejudice the safety function of other equipment claimed in the accident analysis. Additionally, the information provided by this instrument is not employed as a post-accident monitoring parameter.

QUALIFICATION REPORT: N/A METHOD: N/A MPIC

McGUIRE NUCLEAR STATION'- UNITS l'AND 2 Page' . 8A

SUMMARY

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

EQUIPMENT ID: Transmitter - MANUFACTURER: Barton MODEL #: 764 (1) Main Steam Flow (Unit 2)

ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY

' ENVIRONMENT TO WHICH REQUIRED IN ; DEMONSTRATED REQUIRED ' DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)

ENVIRONMENT (3) 7-The Main Steam flow signals are not required for accidents that cause a change in the normal containment operating environment.

Failure of the Main Steam flow transmitters due to the adverse environment following an accident will not prejudice th2 safety function of other equipment claimed in the accident analysis. Additionally, the information provided by thisinstrument is not employed as a post-accident monitoring parameter.

QUALIFICATION REPORT: N/A METHOD: N/A ECSE

r McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 9~

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 2 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: RTD - RCS Temperature (NR) MANUFACTURER: Rosemount MODEL #: 176 KF (1) (Lower Containment) .(NSSS)

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: 332*F Reactor Trip 5 minutes 10.2% 10.2%

Press: 14.8 psig Press: 66 psig (<5 min.) post SLB RH: 100% RH: 100%

Rad: 1X10sR Rad: 1X10sR Chem Spray: N/A Chem Spray: Boric acid and sodium hydroxide soln.

1.146 wt % Boric acid 8.5 pH QUALIFICATION REPORT: WCAP 9157 and Duke letter Parker to Denton dated December 19, 1979 (MCM-1399.03-0438)

METHOD: Test / Analysis

- ECSE

i McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page-10

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 2-LOCATED INSIDE CONTAINMENT EQUIPMENT ID: RTD - RCS Temperature (WR)- MANUFACTURER: Rosemount MODEL #: 176 KS (1) (Lower Containment) (NSSS)

ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIR9HMENT TO WHICH REQUIRED IN. DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)

ENVIRONMENT (3)

Temp: 327 F Temp: 332 F 2 weeks 2 weeks 10.2% 10.2%

Pr:ss: 14.8 psig Press: 66 psig post DBE post DBE a RH: 100% RH: 100%

Rad: 1X10sR Rad: 1X108R s Chem Spray: Boric Chem Spray: Boric

l acid and sodium acid and sodium tetraborate soln. hydroxide soln.

1.46 wt. % Boric acid -

8.5 pH QUALIFICATION REPORT: WCAP 9157 and Supplemental Documentation dated July 20, 1983 and Duke letter Parker to Denton dated December 19, 1979 (MCM-1399.03-0438)

METHOD: Comparison to Model 176 KF, Test / Analysis ECSE

~~

f

~ '

~- s.

}

.c k

McGUIRE' NUCLEAR STATION - UNITS 1 AND 2 ' Page-10A'

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 0 '

-LOCATED INSIDE CONTAINMENT 4

EQUIPMENT ID: RID - Temp. Comp. RVLIS MODEL #:. S8809' MANUFACT[9ER: MINC0 S8810 (1)

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: 420*F 4 months 4 months 15.0 F 11.0 F Press: 14.8 psig Press: 75 psig post DBE 11.19% i .24%

RH: 100% RH: 100% '

R:d: 1X10sR Rad: 1.6X108R Chem Spray: Bor.ic Chem Spray: 2750 PPM acid and sodium H3 80 3 NaOH to 10.7 pH tetraborate soln.

QUALIFICATION REPORT (4): EQDP-ESE-42 WCAP-8687, Supp. 2, E-42A (MCM-1399.03-473)

METHOD: Test ECSE

..?

~

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 .Page 11 SUMARY OF- ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT- ' Rev. 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: _Excore Neutron Detectors MANUFACTURER: ;W IGTD MODEL #: WL-23686 (1) -(Power Range) TNSSS)

- (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 power range neutron detectors are not required for accidents that cause a change in the normal containment operating environment. Further, failure of these detectors as a result of exposure to a harsh environment will not preclude the safety function of other equipment claimed in.the accident analysis. Additionally, the information provided by these detectors is not employed as a post accident monitoring parameter for. operator action. The flux monitoring instrumentation required per Regulatory Guide 1.97 will be provided by other equipment to be added at a later date.

QUALIFICATION REPORT: N/A METHOD: N/A ECSE

4 McGUIRE NUCLEAR STATION - UNITS ~1 AND 2' Page 12 2 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT . Rev. 1:

LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Electric Hydrogen MANUFACTURER: W Sturtevant M00EL #: A (1)- Recombiner {NSSS)

(Upper Containment)

ACCIDENT ENVIRONMENT OPFP LITY OPERABILITY- ACCURACY ACCURACY-ENVIRONMENT TO WHICH REQUI.:EL IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDEhI (% OF SPAN) (% OF SPAN)

ENVIRONMENT (3)

Temp: 180*F Temp: 309'F 3 months 1 year N/A N/A Press: 14.8 psig Press: 62 psig post LOCA post LOCA RH: 100% RH: 100%

Rrd: 8.1X107R Rad: 2X10sR Chem Spray: Boric Chen Spray: Boric acid and sodium acid and sodium tetraborate soln. hydroxide soln.

2500 ppe Boron, 10 pH QUALIFICATION REPORT: WCAP 7820 and Supplements 1-4, WCAP 7709-L and Supplements 1-4 (MCM-1399.36-0004)

METHOD: Test ECSE

.7

.L McGUIRE NUCLEAR STATION - UNITS 1 AND 2 .Page 13

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1-LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Containment Air MANUFACTURER: Joy / Reliance MODEL #: 2XF-330081 (1) Return Fan Motors (Upper Containment)

ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT ,TO Wl:ICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)

ENVIRONMENT (3) ,

l Temp: 180 F Temp: 350*F 2 months 1 year N/A N/A Press: 14.8,psig

- Press: 85 psig post DBE post DBE e

RH: 100%' RH: 100%

, / Pad: . 7.6X107R Rad: 1X109R Chem Spray: Beric Chem Spray: Boric .

acid and sodium acid and sodium -

tetraborate soln. hydroxide soln.

~

3000 ppm Boron, 10.5 pil '

QUALIFICATION REPORT: Test Report X-604 (MCM-1211.00-1147); Test Report

, NUC-9, and-Supplement dated 4/14/60 (MCM-1211.00-1559) ,

METHOD: Test o

m MDSS

_ : g+,0

'McGUIRE NUCLEAR STATION - UNITS 1 AND 2 .Page 14 SUMARY OF. ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT . Rev. 1 LOCATED INSIDE CONTAINMENT 7

EQUIPMENT ID: Hydrogen Skimmer MANUFACTURER: Joy / Reliance MODEL'#: 'l YF-882315' (1) Fan Motors (Upper Containment)

ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY . ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED.

(2) QUALIFIED ACCIDENT (% OF SPAN) (%.0F' SPAN)

ENVIRONMENT (3)

Temp: 180 F Temp: 350*F 2 months 1 year N/A N/A Press: 14.8 psig Press: 85 psig post DBE post DBE RH: 100% RH: 100%

Rad: 7.6X107R Rad: 1X109R Chem Spray: Boric Chen Spray: Boric acid and sodium acid and sodium tetraborate soln. hydroxide soln.

3000 ppe Boron, 10.5 pH QUALIFICATION REPORT: Test Report X-604 (MCM-1211.00-1147); Test Report NUC-9 and Supplement dated 4/14/80 (MCM-1211.00-1559)

METHOD: Test MOSS

r McGUIRE NUCLEAR STATION UNITS 1 AND 2 Page 15 SU MARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAIHMENT EQUIPMENT ID: Valve Motor MANUFACTURER: Rotork MDDEL #: NA-1 (1) Operators (S/N < B-4800)

(Lower Containment) ,.

ACCIDENT ENVIRONMENT OPERA 3ILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (%.0F SPAN) (% OF SPAN)

~ ENVIRONMENT (3) .

t .

~

u :

L Temp: .327 F' Temp: 340*Fs 5 min. 30 days. N/A N/A t

, Press;. 14.8pdq Press: 75 psig (Notes 7 and 8) . post DBE

,RH: 1 "'100%x. RH: 100%

Rad: ' 6.7X107R" Rad: 2X108R ,

ChemSpraf:, Boric Chem Spray: Boric acid and sodium acid and sodium x; , :,

tetraborate soln. hydroxide soln. * '

1750 ppm Boron, s 7-9pH 1 s

i

.I ,

h t W 3. i g ,

SUALIFICATION REPORTi Test Reports N11/4, December'1970; TR 116,, Oct.ober 1973; TR 222, June 1975 (MCM-1205.34-0001) s

' \

-. 3 ,

s.A.

, s >

t -* .

' ~~

METHOD: Teit' -

4 'i e j.

4 < i g.

._. s .

s is g h, 4

-,.< MEQP

% ' ' i .

- - _ - . ~ - - - -

,. s

~ ~e

~ ,

3' McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page ISA

SUMMARY

OF ENVIRONMENTAL QUALIFICATIUN OF CLASS 1E EQUIPMENT Rev. O LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Valve Motor MANUFACTURER: Rotork MODEL #: NA-1 (1) Operators (S/N > B-4800)

(Lower Containment)

ACCIDENT ENVIRONMENT OPERABILITY OPCRABILITY ACCURACY ACCURACY

ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED

! (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)

ENVIRONMENT (3)

Temp: 327 F_ Temp: 385*F 5 min. 30 days N/A N/A Press: 14.8 psig Press: 75 psig (Notes 7 and 8) post DBE RH: 100% RH: 100%

2 Rad: 6.7X107R Rad: 2X108R i Chem Spray: Boric Chem Spray: Boric acid and sodium acid and sodium tetraborate soln. hydroxide soln. -

6200 ppm Boron, 9.5pH QUALIFICATION REPORT: Rotork Report 43979-1-Rev. A dated December 19, 1978 (MCM-1205.34-0010)

METHOD: Test MEQP

____,__m.

.w.

t McGUIRE NUCLEAR STATION -UNITS 1 AND 2 Page 16

SUMMARY

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

EQUIPMENT ID: Valve Motor MANUFACTURER: Limitorque MODEL #: SMB (1) Operators (Order #: 383584-A, (Lower Containment) 391179-A, 391179-B)

ACCIDENT ENVIRONMENT OPERABILITY GPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTFATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)

ENVIRONMENT (3)

Temp: 180 F Temp: 340 F 5 min. 30 days N/A N/A Press: 14.8 psig Press: 105 psig (Notes 7 and 8) post 9BE RH: 100% RH: 100%

Rad: 4X108R Rad: 2X108R Chem Spray: Boric Chem Spray: Boric '

acid and sodium acid and sodium tetraborate soln. hydroxide soln.

3000 ppm Boron, 10.5 pH -

l i

QUALIFICATION REPORT: Limitorque Test Report B0058, Appendix B and C, January 11, 1980 (MCM-1205.34-0002) 1 METHOD: Test MEQP

4 i

.McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 17

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. l' LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Valve Solenoid MANUFACTURER: Valcor MODEL #: V526, V573 .

(1) Operators (Lower Containment) .

ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY l ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED-(2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)

ENVIRONMENT (3)

Temp: 327*F Temp: 346*F Operate upon 31 days N/A N/A Press: 14.8 psig Press: 113 psig receipt of a post DBE

, -RH: 100% RH: 100% safety signal Rad: 7.5X107R Rad: 2X10sR Chem Spray: Boric. Chem Spray: Boric 4

acid and sodium acid and sodium i tetraborate soin. hydroxide soln. ~

j 1720-2200 ppm Boron,

9.5-10.5 pH i

QUALIFICATION REPORT: Test Report QR-52600-5940-2 dated July 5, 1979 (MCM-1205.34-0012) i 1

i METHOD: Test 1

MEQP

/ .

McGUIRE NUCLEAR STATION'- UNITS.1.AND 2. Page 187

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 2

. LOCATED INSIDE CONTAINMENT

. EQUIPMENT ID: Valve MANUFACTURER: V'alcor MGDEL #: V70900-21-1, V70900-21-3.

l (1) Solenoid Operators l (Lower Containment) 1 ACCIDENT ENVIRONMENT CPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT. TO WHICH REQUIRED IN DEMONSTRATED . REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)

ENVIRONMENT (3)

Temp: 327 F Temp: 431*F See JIO See JIO N/A N/A Press: 14.8 psig Press: 87 psig RH: 100% RH: 10 %

Rad: 2.0X107R Rad: 2.2X108R Chem Spray: Boric Chem Spray: Boric a:id and sodium acid and sodium tetraborate soln. hydroxide soln.

2000 ppm Boron, 11.5 pH l

QUALIFICATION REPORT: Valcor Report QR70900-21-1/3 (MCM-1210.04-0193)

METHOD: Test MPIC w

.McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 19

SUMMARY

OF ENVIRONMENTAL-QUALIFICATION OF CLASS 1E EQUIPMENT 'Rev. 1 LOCATED INSIDE CONTAINMENT i . EQUIPMENT'ID: Containment Air Return MANUFACTURER: Rotork MODEL #: 11NAZ1 (1) Isolation Damper Motor j (Upper Containment) i i ACCIDENT ' ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)

ENVIRONMENT (3)

Temp: 180 F Temp: 340*F 5 min. (max) 30 days N/A N/A 1

Press: 14.8 psig Press: 75 psig post DBE post DBE RH: 100% RH: 100%

Rad: 8.1X105R Rad: 2X108R i Chem Spray: Boric Chem Spray: Boric acid and sodium acid and sodium tetraborate soln. hydroxide soln.

1750 ppm Boron, 7-9 pH

QUALIFICATION REPORT: . Test Report N11/4, December 1970; Test Report TR116, October 1973; TR222, June 1975

(MCM-1205.34-0001)

METHOD: Test MDSS

f' i

.McGUIRE NUCLEAR STATION - UNITS l'AND 2 Page 20'

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT' Rev. l' LOCATED INSIDE CONTAINMENT.

EQUIPMENT ID: Valve Solenoid ' MANUFACTURER: LASCO MODEL #: NP8316E34E, NP8316E36E (1) Operators (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: 346*F De-energize upon 30 days N/A N/A Press: 14.8 psig Press: 110 psig receipt of safety post DBE RH: 100% RH: 100% signal Rad: 2.0X107R ' Rad: 2X10sR (<5 min. post DBE)

Chem Spray: Boric Chem Spray: Boric (Note 7) acid and sodium acid and sodium te6raborate soln. hydroxide soln.

3000 ppe Boron,

. 9.5-10.5 pH

't QUALIFICATION REPORT: Test Report AQS21678/TR (MCM-1210.04-0117) ,

METHOD: Test O

MPIC

McGUIRE' NUCLEAR STATION - UNITS 1.AND 2 Page 21 i .

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENi; Rev. 1-LOCATED INSIDE CONTAINMENT.

EQUIPMENT ID: Valve Solenoid MANUFACTURER: Target Rock- MODEL #: 79L (1) ~0perators *

(Lower Containment)

ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY' ACCURACY ACCURACY

, ENVIRONMENT- TO WHICH REQUIRED IN DEMONSTRATED REQUIRED . DEMONSTRATED

'l (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)

ENVIRONMENT (3)

Temp: 327 F Temp: 385 F '(Note 9) 14 days N/A N/A Press: 14.8 psig Press: 66.psig post DBE

! RH: 100% RH: 100%

1.3x108R

Rad: 5.7X107R Rad:

l Chem Spray: Boric Chem Spray: Boron, j acid and sodium acid and hydrazine

tetraborate soln. 6200 ppm Boron, j 8.6-10 pH

(

i l QUALIFICATION REPORT: Test Report 2375, 9/26/79 (MCM-1205.34-0007)

METHOD: Test i

i j MEQP

McGUIRE NUCLLAR STATION - UNITS 1 AND 2' Page 22.

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Differential Pressure Switch- MANUFACTURER: Solon .. MODEL #: 7PSIADW (1) for Damper Control (Upper 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: 140 F Temp: 150*F 1 min. 5 min. 1 0.5 psig 1 0.3 psig Press: 14.8 psig . Press: 15 psig post DBE post DBE -

RH: 100% RH: -100%

Rad: 8.1X105R Rad: 2.1X108R Chem Spray: Boric Chem Spray: Boric acid and sodium acid and sodium tetraborate soln. tetraborate soln.

2000-4000 ppm Boron,

4.7 pH i QUALIFICATION REPORT: Test Reports A293-80 (MCM-1211.00-1505); Test Report A294-80 (MCM-1211.00-1506); Report A-276-80-1 (MCM-1211.00-1489); Test Specification.MCS-1211.00-0006, Supplement 9 METHOD: Test MOSS

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 23

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF-CLASS IE EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Electrical MANUFACTURER: 0.G. O'Brien MODEL #: Types A,B,C,0,E,F,G,H,J,K, (1) Penetrations L,M, cathodic protection (Lower Containment) penetration and spares (Note 10)

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 '4 months 4 months N/A N/A Press: 14.8 psig Press: 15 psig post DBE post DBE RH: 100% RH: 100%

! Rad: 8.5X107R Rad: 2X108R Chem Spray: Boric Chem Spray: Boric acid and sodium acid and sodium tetraborate soln. hydroxide soln.

(Note 11) 4000 ppm Boron, 8.8 pH QUALIFICATION REPORT: D.G. O'Brien, Inc. Test Reports ER-247, ER-252, and ER-227 (Types A,B,C,D,E,F,G,H,J,K,L,M and Cathodic Protection);. W'y le Laboratories Test Report 45869-1 (Types B,C,D,E,F,G,H,J,K,L and M);

) Duke Letter Tucker to Denton dated November 18, 1982 (MCM-1480.08-0001, 2 & 3, and MCM-1361.00-0042)

METHOD: Test / Analysis t

. EPSS

NkGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 23A-

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E-EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Electrical MANUFACTURER: Conax Corporation MODEL #: Type N and BH (1) Penetrations -

(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: 342*F 1 year. 1 year N/A N/A Press: 14.8 psig Press: 80 psig post DBE post DBE RH: 100% RH: 100%

Rad: 1x108R Rad: 2.0x108R l

Chem Spray: Boric Chem Spray: Boric acid

acid and sodium 2050 PPM Boron i

tetraborate-soln. 6-10 pH l

l QUALIFICATION REPORT (4): Conax Qualification Report No. IPS-1037 (MCM-1361.00-0061)

METHOD: Test / Analysis EPSS i

McGUIRE NUCLEAR STATION - UNITS 1-AND 2 Page 24

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1-LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Cable- MANUFACTURER: Okonite ~MODEL #: EP, EP/Hypalon and FREP (1) Control and Power Insulation (Procurement (Lower Containment) Specs: MCS-1354.01-1,2, 3&4 MCS-1354.02-4,6&9)

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: 345 F 30 days 130 days N/A N/A Press: 14.8 psig- Press: 104 psig aast DBE post DBE RH: 100% RH: 100%

Rad: 6.7X107R Rad: 2X108R Chem Spray: Boric . Chem Spray: Boric acid and sodium acid, sodium tetraborate soln. hydroxide and sodium thiosulfate soln.

3000 ppm Boron, 10.5 pH QUALIFICATION REPORT: Test Reports N1 dated May 2, 1975 (MCM-1354.00-0010); G1 dated February 17, 1976 (MCM-1354.00-0045),

G3 dated June 28, 1979 (MCM-1354.00-0012); FN-1 dated July 3, 1978 (MCM-1354.00-0013)

METHOD: Test EPSS

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 25

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Cable - MANUFACTURER: Okonite MODEL #: Tefzel 280 Insula, tion (1) Control (Procurement Spec:

(Lower Containment) MCS-1354.04-6)

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: 341*F 4 months . 130 days N/A N/A Press: 14.8 psig Press: 112 psig post DBE RH: 100% RH: 100%

Rad: 8.5X107R Rad: 2X10sR Chem Spray: Boric Chem Spray: Boric acid and sodium acid, sodium tetraborate soln. hydroxide and sodium thiosulfate sa'a n.

3000 ppm Baron, 10.5 pH QUALIFICATION REPORT: Test Report K-0-1, September 1979 (MCM-1354.00-0011) and K-8-1, April 4, 1981 (MCM-1354.00-0044)

METHOD: Test EPSS

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 26

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT. Rev. 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Cable - MANUFACTURER: . Anaconda MODEL-#: EP and EP/Hypalon (1) Control and Power Insulation (Procurement (Lower Containment) Specs: MCS-1354.01-2 &

4 & MCS-1354.02-3,6&9)

ACCIDENT ENVIRONMENT OPERABfLITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% 0F SPAN) (% OF SPAN)

ENVIRONMENT (3).

Temp: 327 F Temp: 346*F 3 months 4 months N/A N/A Press: 14.8 psig Press: 113 psig post DBE post DBE RH: 100% RH: 100%

Rad: 9X107R Rad: 2X108R Chem Spray: Boric Chem Spray: Boric acid and sodium acid, sodium tetraborate soln. hydroxide and

, sodium thiosulfate soln.

3000 ppm Boron, 10.5 pH QUALIFICATION REPORT: Test Reports F-C4350-2 (MCM-1354.00-0008) and F-C4350-3 and Supplement (MCM-1354.00-0009)

METHOD: Test EPSS

+

McGUIRE NUCLEAR STATION UNITS 1 AND 2 Page 27

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Cable - MANUFACTURER: Brand Rex MODEL #: XLPE Insulation (1) Control (Procurement Specs:

(Lower Containment) MCS-1354.02-4,5,7 & 9,

& MCS-1354.04-14)

ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY- ACCURACY ACCURACY l ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN)

ENVIRONMENT (3)

Temp: 327*F Temp: 346*F 30 days 120 days N/A N/A l Press: 14.8 psig Press: 113 psig post DBE post DBE RH: 100% RH: 100%

Rad: 7.5X107R Rad: 2X10sR Chem Spray: Boric Chem Spray: Boric acid and sodium acid and sodium tetraborate soln. hydroxide soln.

6200 ppm Boron, 10 pH a QUALIFICATION REPORT: Test Reports FC4113 (MCM-1354.00-0007); FC5120-1 (MCM-1354.00-0023); and FC5120-3 (MCM-1354.00-0024)

METHOD: Test

,l EPSS l

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 28-

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT- Rev.-1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Cable - MANUFACTURER: Eaton (Samuel Moore) MODEL #: EP/Hypalon Insulation (1) Instrumentation (Procurement Specs: ,

(Lower Containment) MCS-1354.03-1, 2,3&5

& MCS-1354.04-2&5)

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: 14.0 psig Press: 105 psig post DBE post DBE RH: 100% RH: 100%

Rad: 7.5X107R Rad: 2X108g Chem Spray: Boric Chem Spray: Boric acid and sodium acid and sodium tetraborate soln. hydroxide soln.

2000 ppm Boron, 9-11 pH QUALIFICATION REPORT: Test Report F-C3683 (MCM-1354.00-0006)

METHOD: Test i

EPSS

McGUIRE_ NUCLEAR STATION - UNITS 1 AND 2. Page 29

SUMMARY

-OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT .Rev. 2 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Cable Termination / MANUFACTURER: Raychem MODEL #: WCSF-N Sleeves and (1) Splice Material Breakouts (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) i Temp: 327*F Temp: 357*F 4 months 4 months N/A N/A Press: 14.8 psig Press: 70 psig post DBE post DBE RH: 100% RH: 100%

Rad: 8.5X107R Rad: 2X108R

! Chem Spray: Boric Chem Spray: Boric acid and sodium acid and sodium tetraborate soln. hydroxide soln.

3000 ppm Boron, 10.5 pH QUALIFICATION REPORT: Test Reports F-C4033-3, (MCM-1367.01-0001) 71100, (MCM-1367.01-0003), and 2001 (MCM-1354.00-0034) 4 I

METHOD: Test / Analysis EPSS b

Page 30 McGUIRE NUCLEAR STATION - UNITS 1 AND 2

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1-LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Stem-Mounted Limit MANUFACTURER: NAMCO MODEL #: EA 180, EA 740 (1) Switches (Lower Containment)

ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED i (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF SPAN) 1 ENVIRONMENT (3) i -

Temp: 327 F Temp: 340 F 5 min 30 days N/A N/A

, Press: 14.8 psig Press: 66 psig (Note 8) post DBE I RH: 100% RH: 100%

j Rad: 6.7X107R Rad: 2X108R

Chem Spray: Boric Chem Spray: Boric acid and sodium acid and sodium tetraborate soln. hydroxide soln.

3000 ppm Boron, 10.5 pH i

f QUALIFICATION REPORT: Namco Reports QTR-106, Rev. 3 dated September 2, 1981 (MCM-1205.34-0009), and QTR 111, Rev. O dated October 1, 1981 (MCM-1205.34-0008) f METHOD: Test MEQP

r I

McGUIRE NUCLEAR STATION - UNITS 1 AND 2' 'Page 31

SUMMARY

OF. ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 2 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Seal Material for MANUFACTURER: 3M MODEL'#: Scotch Cast 9 (XR-5240)

(1) Cable Entrances and Termination

. Fittings (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)

Te;p: 327 F Temp: 340 F 4 months 4 months N/A N/A Press: 14.8 psig Press: 15 psig post DBE 5

RH: 100% RH: 100%

Rad: 6.7X107R Rad: 2X108R Chem Spray: Boric Chem Spray: Boric

acid and sodium acid and sodium l tetraborate soln. hydroxide soln.

I 4000 ppm Boron.

QUALIFICATION REPORT: W'le y Test Report 44390-1, Rev. A (MCM-1364.00-0005)

METHOD: Test / Analysis i

i 4

EPSS i

't

-McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 32

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Containment Radiation MANUFACTURER: ' General Atomic MODEL #: RD-23 Ionizatio.

(1) Monitors-High Range Chamber (Lower Containment)

ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT .T0 WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2)

QUALIFIED ACCIDENT .

(% OF SPAN) (% OF SPAN)

ENVIRONMENT (3)

Temp: 240 F Temp: 315*F 2 weeks 18 days Note 13 Note 13 l' Press: 14.8 psig Press: 70 psig post LOCA post LOCA RH: 100% RH: 100%

Rad: 8X107R ~ Rad: Note 12 Chem Spray: Boric Chem Spray: Boric J acid and sodium acid and sodium

tetraborate soln. thiosulfate and

, sodium hydroxide, j 3000 ppm Boron, 10.5 pH-j QUALIFICATION REPORT: General Atomic. Test Report E-254-960 dated May 1, 1981 (MCM-1346.05-0137) t 1

)i i METHOD: Test / Analysis I

4 l

ECSE

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 33

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1

' LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Cable for Containment MANUFACTURER: Rockbestos MODEL #: RSS-6-104-1081 (1) Radiation Monitors High Range (Second Generation)

(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: 240 F Temp: 315*F 2 weeks 1 year N/A N/A' i

Press: 14.8 psig Press: 70 psig post LOCA post LOCA i RH: 100% RH: 100%

l Rad: 8X107R Rad: 2X108R Chem Spray: Note Chem Spray: Boric i 14 acid and sodium i

thiosulfate and i sodium hydroxide i 3000 ppm Boron, l 10.5 pH t

j QUALIFICATION REPORT: Rockbestos Test Report 2806 (MCM-1354.00-0040) 1 i METHOD: Test l

l

) ECSE 1

5

McGUIRE NUCLEAR STATION.- UNITS 1 AND 2 Page 34

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIP."1ENT Pav. 2' LOCATED INSIDE CONTAINMENT

. EQUIPMENT ID: Acoustical Valve Position MANUFACTURER: TEC MODEL #: 2273A Accelerometers (1) Monitors-accelerometers, charge 504A Charge Converter

-converters and cables (Lower Containment)- 160-2 Transient Shield

2273-C2 Cable Assembly.

ACCIDENT ENVIRONMENT OPERABILITY . OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH . REQUIRED IN ' DEMONSTRATED REQUIRED DEMONSTRATED i (2) QUALIFIED ACCIDENT (% OF SPAN) (% OF-SPAN) i ENVIRONMENT (3) 1 ?

, Temp: 327 F Temp: .510*F 2 weeks 1 month N/A N/A j Press: 14.8 psig Press: 85 psig post DBE post DBE

, RH: 100% RH: 100%

Rad: 8X107R Rad: 2X108R 4

Chem Spray: Boric Chem Spray: Boric l acid and sodium acid, hydrazine and tetraborate soln. sodium phosphate i soln. 2300 ppm Boron, i 7-7.5 pH i

QUALIFICATION REPORT: TEC Test Report 517-TR-03 Rev. 3(MCM-1346.17-0009, 10,11,12,13,14 & 16) l I,

j METHOD: Test f

i 1

ECSE

"U .,

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 35

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT . Rev. 2 LOCATED INSIDE CONTAINMENT EQUIPMENT ID: Incore Thermocouple System MANUFACTURER: Combustion Engineers MODEL #: TN/A (1) Cables and Connectors ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY- ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2) QUALIFIED ACCIDENT (% OF SPAN) '(% OF SPAN)

ENVIRONMENT (3) w Te:p: 327 F Temp: 460 F <4 months 4 months N/A N/A Press: 14.4 psig Press: 100 psig post-DBE. post-DBE RH: 100% RH: 100%

Rad: 1.3X108R Rad: 2.1X10sR Chem Spray: Boric Chem Spray: Boric acid and sodium acid and sodium tetraborate soln. hydroxide 3000 ppm Boron pH 10.3 QUALIFICATION REPORT: Combustion Engineering Report No. 17682-CCE-SR80-1, Rev. 00 METHOD: Test Note: Unit 1 in-containment components installed Unti 2 in-containment components to be installed prior to start-up following first refueling outage.

) -

ECSE I

~

Page IN1 Revision 1 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.

Specific locations with regard to upper or lower containment are noted for each equipment type.

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.

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 Sprau: 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 cont.'nment accident environment are as identified in FSAR Table 3.11.1-1 (Rev. 43).

Note 4 Deleted

. _. . _ . . .__..a

er .

Page IN2 Revision 2 Note 5 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 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 gaga to track the temperature of the circuit board more closely during the first minute and limited the positive error to less than 4%. In other words, the temperature difference between the s'train gage and the circuit board has been reduced to a level compatible to McGuire functional requirements.

Note 6 Deleted.

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 service can reasonably be expected.from this equipment.

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.

Note 10 Electric penetration types B, C, F, G, H and K are'the only penetrations required to function electrically in the containment accident environment.

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

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

l l

l

Page 1N3 Revision 1 Note 12

'The manufacturer's test' report states that the detector assembly is constructed of metal 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 120% 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.

Note 15 Deleted-Note 16 Deleted l

l

[

l b ._

e ATTACHMENT 2

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT LOCATED IN THE ANNULUS Page Rev. Page Rev. M Rev.

1 2 la 0

. ~2 1 2A 0 -

.3 1 -

4 1 5 1-5A 0 '

6 1 7 1

-7A 0 8 1 8A 0 9 1 9A D 1

10 1 11 1 '

12. 1 ,

13 1 14 1 s

15' 1 '

1 16 2~ s ,

/

17 'D 18 1 1 19 1 20 1 ; (. -

21 1 <

22 1 'e,'

23 1 2N1 g -

l D = Deletion 1 1

I l-i t

1 l

l Rev. 3 i

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 . Page 1 St# NARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 2 LOCATED IN THE ANNULUS ;

EQUIPMENT ID: Transmitter-Containment Sump MANUFACTURER: Barton MODEL #: 386A Level ACCIDENT ENVIRONMENT OPERABILITY. OPERABILITY ACCURACY ACCURACY i ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED- DEMONSTRATED

(1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN)

ENVIRONMENT j

Temp: 142 F Temp: 172*F 4 months 1 year 113% 113%

RH: 100% RH: 100% post DBE post DBE Rad: 1.2X107R Rad: 2X10sR QUALIFICATION REPORT: Wyle Test Report 43904-1, Vol. I - Rev. C, Vol. II - Rev B (MCM-1210.04-0016)

METHOD: Test l

MPIC 4

-- _ _ _ _ - _ _ _ __.-______.__w

'McGUIRE NUCLEAR STATION - UNITS l'AND 2 Page la

SUMMARY

_0F ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT _ Rev. 0 ~j~

LOCATED IN THE ANNULUS EQUIPMENT ID: Transmitter-Annulus Pressure t MANUFACTURER: Sarton MOUEL #- 386N **

I ACCIDENT ENVI10NMENT OPERABILITY OPERAB!LITY ACCURACY ACCURACY ENVIRONMENT TO UHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED.

(1) QUALIFIED ! ACCIDENT' (2) (% OF SPAN) (% OF SPAN) i ENVIRONMENT l

< Te p: 142 F Temp: 172 F 4 months 1 year 113% 113%

RH: 100% RH: 100% post DBE post DBE

! Rad: 1.2X107R Rad: 2X10sR 1

1 QUALIFICATION REPORT: Wyle Test Report 43904-1, Vol. I - Rev. C, Vol. II - Rev B (MCM-1210.04-0016)

i METHOD: Test

,; w:

4 MPIC

c r li. .,,,

^

McGUIRE NUCLEAR STATION - UNITS 1 ANO-2 Page 2 SUPMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS-IE EQUIPMENT- Rev. IL LOCATED IN THE ANNULUS EQUIPMENT ID: Transmitter-RCS Pressure '(WR) MANUFACTURER: Rosemount MODEL #: 1153GA9 (Unit 1)

ACCIDENT' - ENVIRONMENT OPERABILITY OPERABILITY ACCURACY- ACCURACY ENVIRONMENT TO WHICH - Q QUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED' (1) QUALIFIEP ACCIDENT (2) (% OF SPAN) (% OF SPAN)

ENVIRONMENT 1

Temp: 142 F Temp: 350*F 4 months 1 year i 10% +6.95%

RH: 100% RH: 100% . post DBE post DBE Rad: 1.0x106R Rad: 4X107R I

, QUALIFICATION REPORT: Rosemont Test Report 3788, Rev. A-(MCM-1210.04-0173)

METHOD: Type Test Similarity l

j j MPIC

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 2A SUM 4ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. O LOCATED IN THE ANNULUS 1

EQUIPMENT ID: Transmitter-RCS Pressure (WR) MANUFACTURER: Rosemount MODEL #: 1153GD9 (Unit 2)

ACCIDENT- ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED ACCIDENT. (2) (% OF SPAN) (% OF SPAN)

ENVIRONMENT l

I Temp: 142 F -Temp: 350*F 4 months 1 year i 10% -5.5%

l RH: 100% RH: 100% post DBE post DBE i Rad: 2x10GR Rad: 4X107R v

i

, QUALIFICATION REPORT: Wyle Test Report 45592-1 (MCM-1210.04-0178) l METHOD: Type Test i

i i

MPIC

4 9

McGUIRE NUCLEAR STATION - UNITS 1'AND 2 . Page 3

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 ,

LOCATED IN THE ANNULUS 4 EQUIPMENT ID: Transmitter-RCS Pressure (WR) MANUFACTURER: Barton MODEL #: 763 (Lot 2)

(Unit 1)

\

ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY- ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED ACCIDENT (2) (% OF. SPAN) (% OF SPAN)-

ENVIRONMENT L

Temp: 142*F Temp: 380*F 2 weeks 1 year i 10% i 7.7%

RH: 100% RH: 100% post DBE post DBE Rad: 1.2X107R Rad: SX107R 1

i QUALIFICATION REPORT: WCAP 9885 (MCM-1399.03-0439) '

i i >

METHOD: Test i

ECSE

' ~

i :q. ;

i

, m l McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 4 SUMARY OF ENVIRONMENTAL QUALIFICATION OF. CLASS 1E EQUIPMENT :Rev. 1 l LOCATED IN.THE ANNULUS l

i -EQUIPMENT ID: Transmitter - RCS Pressure (WR) MANUFACTURER: Barton MODEL #: 763 (Lot 5)

(Unit 2)

i i

I ACCIDENT ENVIRONMENT OPERABILITY' OPERABILITY ACCURACY ' ACCURACY ~

ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED i

, (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN) 'j

ENVIRONMENT l

4 Temp: 142 F Temp: 420 F -2 weeks 1 year i 10% 110%

RH: 100% RH: 100% post DBE post DBE Rad: 1.2X107R Rad: SX107R

! i l

i QUALIFICATION REPORT: WCAP 8587 Supp. 1, EQDP-ESE-1 and WCAP 8687 Supp. 2, E01A (MCM-1399.03-0472) ,

i l

METHOD: Test I

l 1

ECSE l

y McGUIRE NUCLEAR STATION - UNITS 1.AND 2 Page 5 SU W ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT. Rev. 1 LOCATED IN THE ANNULUS 1

EQUIPMENT ID: Valve Solenoid Operators MANUFACTURER: Valcor MODEL #: V70900-21-3 i

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: 346"F De-energize upon 1 year N/A N/A RH: 100% RH: 100% receipt of a safety post DBE Rad: 1X104R Rad: 2X10sR signal (5 minutes post DBE)

(Note 3)

QUALIFICATION REPORT: Test Reports QR-52600-515-Rev. B (MCM-1210.04-0115); QR-70900-21-1-Rev. A (MCM-1210.04-0118);

MR7095-21-3-1 (MCM-1210.04-0119)

METHOD: Test / Similarity ,

MPIC

.McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page SA

SUMMARY

-0F ENVIRONMENTAL QUALIFICATION OF CLASS'1E EQUIPMENT Rev. O' LOCATED IN THE~ ANNULUS EQUIPMENT ID: Valve Solenoid Operators MANUFACTURER: Valcor MODEL #: V526 ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY

ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED # ACCIDENT (2) (% OF SPAN) (% OF SPAN) i ENVIRONMENT i

Temp: 142 F Temp: 346*F De-energize upon 1 year N/A N/A RH: 100% RH: 100% receipt of.a safety post DBE Rad: 1X104R Rad: 2X108R signal (5 minutes

post DBE)

(Note 3) i

, QUALIFICATION REPORT: Test Report QR-52600-5940-2 dated July 5, 1979 (MCM-1205.34-0012)

METHOD: Test MEQP

.N " ' R 4 .

4

-P

~

McGUIRE NUCLEAR STATION - UNITS 1 AND'2 Page 6-SUMARY OF EINIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT ; Rev. 1 ,

.: LOCATED IN THE ANNULUS EQUIPMENT ID: Valve Solenoid Operators MANUFACTURER: ASCO MODEL'#: NP8316E34E 4

l ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY

, ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED i (1) QUALIFIED ACCIDENT- (2) -(% OF SPAN) (% OF SPAN) j . ENVIRONMENT l

l Temp: 142*F Temp: 346*F .De-erorgize upon 1 year N/A N/A RH: 100% RH: 100% receipt of a safety post DBE Rad: 1X104R Rad: 2X10sR signal (5 minutes

! post DBE)

(Note 3) j QUALIFICATION REPORT: Test Report AQS21678/TR (MCM-1210.04-0117) l l METHOD: Test 1

1 MPIC

McGUIRE NUCLEAR STATION -' UNITS 1 AND 2 Page 7 SUP9tARY.OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS-EQUIPMENT ID: Valve Motor Operators MANUFACTURER: Rotork MODEL #: NA-1 (S/N <B-4800).

ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMGNSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN)

ENVIRONMENT l

t i

l Temp: 142*F Temp: 340*F 5 minutes 1 year N/A N/A

.; RH: 100% RH: 100% post DBE post DBE

.! Rad: 1X104R Rad: 2X10sR (Note 3) i 4

4 QUALIFICATION REPORT: Test. Reports N 11/4 dated 12/70; TR-116 dated 10/73; TR-222 dated 6/75 (MCM-1205.34-0001)

METHOD: Test MEQP

1

'1 McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 7A' f

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 0 l LOCATED IN THE ANNULUS l Valve Motor Operators MANUFACTURER: Rotork HODEL #: NA-1 ;

EQUIPMENT ID: '

(S/N >B-4800)

ACCURACY i ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY TO WHICH DEMONSTRATED REQUIRED DEMONSTRATED ,

ENVIRONMENT REQUIRED IN (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN)

ENVIRONMENT l

Temp: 142 F Temp: 385*F 5 minutes 1 year N/A N/A RH: 100% RH: 100% post DDE post DBE R d: IX104R Rad: 2X10sR (Note 3) i QUALIFICATION REPCRT: Wyle 43979-1, Rev. A, dated December 19, 1978 (MCM-1205.34-0010)

METHOD: Test MEQP

4 s

1!

l 4

McGUIRE NUCLEAR STATION'- UNITS 1 AND 2 . Page 8 .j SUPMARY. OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT

Rev. 1 LOCATED IN THE ANNULUS -.

EQUIPMENT ID: Valve Motor Operators MANUFACTURER: Rotork- MODEL #: 'NA-2

i ACCIDENT ENVIRONMENT OPERABILITY. OPERABILITY ACCURACY- ACCURACY 1 ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED

, (1) QUALIFIED ACCIDENT' (2) .(% OF SPAN)- (% OF SPAN),

ENVIRONMENT-Temp: 142*F Temp: 163*F 5 minutes 1 year N/A- N/A RH: 100% RH: 100% post DBE post DBE Rad: 1X104R Rad: 3X107R (Note 3) i <

i 4

QUALIFICATION REPORT: Test Reports N11/4 dated 12/70, TR-116 dated 10/73, TR-222 dated 6/75 (MCM-1205.34-0001) l j METHOD: Test MEQP 4

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 8A SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 0 LOCATED IN THE ANNULUS EQUIPMENT ID: Valve Motor Operators MANUFACTURER: Limitorque- MODEL'#: SMB (Order #: 383584-A, 391179-A, 391179-B)

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: 340*F 5 minutes 1 year N/A N/A RH: 100% RH: 100% post DBE post DBE Rad: 1X104R Rad: 2x108R (Note 3)

QUALIFICATION REPORT: Limitorque Test Report B0058, Appendix B and C, dated 01/11/80 (MCM-1205.34-0002)

METHOD: Test i

i MEQP I _ _ _ _ _ _

I McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 9' SUPMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS EQUIPMENT ID: Stem-Mounted Limit Switches MANUFACTURER: NAMCO MODEL #: EA-180 ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY . ACCURACY l ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED . DEMONSTRATED (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN)

ENVIRONMENT 1

Temp: 142*F Temp: 385*F 5 minutes 1 year N/A N/A

. RH: 100% RH: 100% post DBE post DBE Rad: 1X104R Rad: 2.3X10sR i

QUALIFICATION REPORT: NAMCO Report QTR106, Rev. 3, dated 09/02/81 (MCM-1205.34-0009) 1 i METHOD: Test j

MEQP

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 10 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS EQUIPMENT ID: Limit Switch MANUFACTURER: Microswitch MODEL #: LSM4N l

! ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY' ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN)

ENVIRONMENT This equipment will be removed from safety power before startup after the first refueling. This equipment provides damper

. position indication only and is not used as a basis for any required operator action. Additionally, failure of these i switches will not prevent satisfactory accomplishment of any required safety function.

i l

i i

4 MDSS

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 11

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS I

EQUIPMENT ID: Cable - Triaxial Instrumentation MANUFACTURER: Boston Insulated MODEL #: XLPE Insulation (Procurement Spec:

MCS-1354.04-13)

I 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: 300 F 4 mcnths 1 year N/A N/A RH: 100% RH: 100% post DBE post DBE R-d: 3X107R Rad: 2X10sR l

i QUALIFICATION REPORT: B.I.W. Test B912 (MCM-1354.00-0017) l F METHOD: Tes,t EPSS

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 12 SUPetARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. l' LOCATED IN THE ANNULUS EQUIPMENT ID: Cable - Instrumentation MANUFACTURER: Brand Rex MODEL #: XLPE Insulation (Procurement Specs:

MCS-1354.03-8 &

MCS-1354.04-6)

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: 346*F 4 months 1 year .N/A N/A RH: 100% RH: 100% post DBE post DBE Rad: 3X107R Rad: 2X10sR

]

QUALIFICATION REPORT: Brand Rex Test FC4113 (MCM-1354.00-0007), FC5120-1 (MCM-1354.00-0023) and FC5120-3 (MCM-1354.00-0024)

METHOD: Test EPSS l

i

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 13 SUPMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT' Rev. 1

. LOCATED IN.THE ANNULUS EQUIPMENT ID: Cable - Instrumentation MANUFACTURER: Eaton (Samuel Moore) MODEL #: EP/Hypalon Insulation (Procurement Specs:

MCS-1354.03-1,2,3 & 5

& MCS-1354.04-2 & 5)

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: 340*F 4 months 1 year N/A N/A RH: 100% RH: 100% post DBE post DBE Rad: 3X107R Rad: 2X10sR i

QUALIFICATION REPORT: Samuel Moore Test FC3683 (MCM-1354.00-0006)

METHOD: Test EPSS l

I

y- % -m -- -

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 -Page 14 ,

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS EQUIPMENT ID: Shielded Pair Armored Jacketed MANUFACTURER: Eaton (Samuel Moore) MODEL #: PVC Insulation Instrumentation Cable 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: 340 F 4 months 1 year N/A N/A RH: 100% RH: 100% post DBE post DBE rid: 3X107R Rad: SX107R

! QUALIFICATION REPORT: Duke Test Report TR-032 (MCM-1354.00-0022) i METHOD: Test I

EPSS I

)

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 'Page 15

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF. CLASS 1E EQUIPMENT Rev.-1 LOCATED IN THE ANNULUS EQUIPMENT ID: Cable - Shielded Pair Armored . MANUFACTURER: Brand Rex MODEL #: PVC Insulation Jacketed Instrumentation 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: 340*F 4 months 1 year N/A N/A RH: 100% RH: 100% post DBE post DBE Rid: 3X107R Rad: SX107R

! QUALIFICATION REPORT: Duke Test Report TR-032 (MCM-1354.00-0022)

METHOD: Test l

EPSS

McGUIE NUCLEAR STATION - UNITS 1 AND 2 Page 16 SUW4ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 2

. LOCATED IN THE ANNULUS EQUIPMENT ID: Cable - Instrumentation MANUFACTURER: Okonite MODEL #: Hypalon Insulation (Procurement Spec:

MCS-1354.03-4)

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: 340 F 4 months 1 year N/A N/A RH: 100% RH: 100% post DBE post DBE Rad: 3X10 7R Rad: 3.5X107R QUALIFICATION REPORT: 110E, November 12, 1970 (MCM-1354.00-0016) and Duke Test Report TR-032, November 5, 1982 (MCM-1354.00-0022)

METHOD: Test EPSS

^

'McGUIRE' NUCLEAR STATION - UNITS 1 AND 2 Page 18 SUMARY OF' ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED-IN THE ANNULUS.

EQUIPMENT ID: Cable - Control MANUFACTURER: Okont te' .MODEL #: EP/Hypalon, FREP,'& EP-Insulation (Procurement.

. Specs: MCS-1354.02-4,6

& 9) .

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: 346*F 4 months 1 year N/A N/A RH: 100% RH: 100% post DBE post DBE Rrd: 3X107R Rad: 2X10sR i

QUALIFICATION REPORT: Okonite Test Reports N1, May 2, 1975 (MCM-1354.00-0010); FN-1, July 3, 1978 (MCM-1354.00-0013) l l METHOD: Test ,

i EPSS-l l

\

McGUIRE NUCLEAR STATION --UNITS 1 AND 2 Page 19 SUPMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 l LOCATED IN THE ANNULUS j EQUIPMENT ID: Cable - Control MANUFACTURER: Eaton (Samuel Moore) MODEL #: EP/Hypalon Insulation (Procurement Spec:

1 MCS-1354.03-6) 1 i ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED ;

(1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN) l ENVIRONMENT Temp: 142*F Temp: 340*F 4 months 1 year N/A N/A RH: 100% RH: 100% post DBE post DBE

Rad: 3X107R Rad: 2X10sR i

I l

j QUALIFICATION REPORT: Samuel Moore Test FC3683 (MCM-1354.00-0006) i

. i METHOD: Test i EPSS

.. p 4

McGUIRE NUCLEAR STATION.- UNITS 1 AND 2 Page 20 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT Rev. 1 LOCATED IN THE ANMULUS i

EQUIPMENT ID: Cable - Control MANUFACTURER: Anaconda MODEL 1: EP/Hypalon Insulation (Procurement Specs:

MCS-1354.02-3, 6 & 9)

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: 346*F 4 months 1 year N/A N/A '

RH: 100% RH: 100% post DBE post DBE Rad: 3X107R Rad: 2X108R QUALIFICATION REPORT: Anaconda Test FC4350-2 (MCM-1354.00-0008), FC4350-3 and Supplement (MCM-1354.00-0009)

METHOD: Test EPSS

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 21

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS-1E EQUIPMENT Rev. 1 LOCATED IN THE ANNULUS EQUIPMENT ID: Cable - Power MANUFACTURER: Anaconda MODEL #: EP/Hypalon and EP Insulation (Procurement Specs: MCS-1354.01-2

& 4)

ACCIDENT ENVIRONMENT OPERABILITY CPEEABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEM0t:STRATED REQUIRED DEMONSTRATED (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN)

ENVIRONMENT Temp: 142 F Temp: 346*F 4 months 1 year N/A N/A RH: 100% RH: 100% post DBE post DBE Rad: 3X107R Rad: 2X10sR QUALIFICATION REPORT: Anaconda Test FC4350-2 (MCM-1354.00-0008), FC4350-3 and Supplement (MCM-1354.00-0009)

METHOD: Test EPSS

3 4

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 22 4

SumARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 '

LOCATED IN.THE_ ANNULUS l EQUIPMENT ID: Cable - Power MANUFACTURER: Okonite MODEL #: EP'and EP/Hypalon Insulation (Procurement j Specs: MCS-1354.01-1, l 2, 3 & 4)

ACCIDENT ENVIRONMENT + OPERABILITY OPERABILITY ACCURACY ACCURACY i ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED ACCIDENT (2) (% OF SPAN) (% OF SPAN)

! ENVIRONMENT i

i Temp: 142*F Temp: 346*F 4 months 1 year N/A N/A J RH: 100% RH: 100% post DBE post DBE l Rad: 3X107R Rad: 2X10sR i

QUALIFICATION REPORT: Okonite Test ... 1, May 2, 1975 (MCM-1354.00-0010); G1, February 17, 1976 (MCM-1354.00-0045);

l G-3, June 28, 1S _ . cM-1354.00-0012) i METHOD: Test l EPSS I

W ^ '~

.. . . : :.. 2 .

p.

Page 2N1 Revision 2 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 environme.it are as follows:

Temperature: 142*F peak; Annulus temperature excursion due to a main steam line break inside containment as shown in calculation MCC-1223.14-00-0006.

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 to reach 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.

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

Note 4 Deleted Note 5

Deleted I _

e- ;- -

g to ,

a.

ATTACHMENT 3

SUMMARY

OF ~ ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT Page_ Rev. M Rev. M Rev.

I 1- 33 2 2- 1 .33a 2 3 1. 34 2 4 1 34a 2 5 1 35 2 6 1 35a 2-7 1 36 2 8 1 36a 2 9 0 37 2 10 2 37a 2 11 1 38 1 12 1 39 1 13 1 40 1 14 D- 41 1

.15 -1 42 1 16 1 43 1 16a- 0 44 1 -

17 1 45 1 18 1 46 1

~19 1 47 1 20 1 48 1

21 1 49 1 22 2 50 1 22a 2 51 23 1 52 1 24 2 53 1 24a 2 54 1 24b 2 55 1 24c 2 56 1 25 2 57 1 25a 2 58 1 26' 2 59 1 26a 2 60 1 27 2 61 1 28 1 62 1 29 2 63 1 29a 2 64 1 30 1 65 0 30a 2 66 2 31 2 66a 2 31a 2 3N1 2 32 1 3N2 1 32a D r r D = Deletion

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

.s~

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 . Page 1

SUMMARY

OF ENVIRON >. TAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE Cur 4TAINMENT AND EXPOSED TO HELB ENVIRONMENT-EQUIPMENT ID: Containment Spray MANUFACTURER: Westinghouse, MODEL #: 73F56019-1573, Pump Motors Buffalo 73F56019-2573, 73F56019-3573,'73F56019-4573 HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

This equipment is not required to function for HELBs that affect its environment i,

,'{

4 QUALIFICATION REPORT: Duke Report MDS/PDG-77-1, Calculation MCC-1206.47-00-0001 l

METHOD: Analysis EPSR

McGUIRE sdCLEAR. STATION - UNITS 1 AND 2 Page 2 SUMARY OF ENVIRONMENTAL' QUALIFICATION OF CLASS 1E EQUIPMENT- Rev. 1 LOCATED OUTSIDE CONTAlhMENT AND EXPOSED TO HELB ENVIRONMENT ; _

EQUIPMENT ID: Residual Heat Removal MANUFACTURER: Westinghouse, MODEL #: 71F13454-1572,'71F13454-Pump Motors Buffalor

~ '

2572, 71F13495-1572,

.71F13495-2572 HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY

ENVIRONMENT TO WHICH ' REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) . QUALIFIED HELB .

(% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

This equipment is not required to function for HELBs that affect its environment QUAllFICAT10N REPORT: Duke Report MDS/PDG-77-1, Calculation MCC-1206.47-00-0001 METHOD: Analysis l EPSR

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 3

SUMMARY

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

~ EQUIPMENT ID: Safety Injection MANUFACTURER: Westinghouse, MODEL #: 73F69618-IS75, 73F69618-Pump Motors and Spares Buffalo . 2S75, 73F69618-3575, 73F69618-4575 81F32009-1582-12 HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSIRATED REQUIRED DEMONSTRATED

(1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2) 4 Temp: 212 F Temp: 212 F Continuous continuous N/A N/A I

4 4

QUALIFICATION REPORT: WCAP 8754 (MCM-1318.00-0026) and Duke analyses (MCC 1381.05-00-0101, MCC 1381.05-00-0102) i l

METHOD: Test and Analysis

. EPSR

_ . l s.

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 4 1

SUMMARY

OF' ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT- Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HEL8 ENVIRONMENT i

1 i EQUIPMENT ID: Centrifugal' Charging MANUFACTURER: Westinghouse, MODEL #: 72F44587-1573, 72F44587-

Pump Motors and Spares Buffalo 2S73, 72F44587-3573

72F44587-4S73

! 81F32008-1582-Il l HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTPATED (1) QUALIFIED 'HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 212 F Temp: 212 F Cor.tinuous Continuous N/A N/A i

i QUALIFICATION REPORT: WCAP 8754 (MCM-1318.00-0026) and Duke analyses (MCC 1381.05-00-0101, MCC 1381.05-00-0102)

METHOD: Test and Analysis EPSR

1:

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 5

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS'1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Nuclear Service Water MANUFACTURER: Westinghouse, MODEL #: 72F36530-1575,.72F36531-Pump Motors and Spares Buffalo 1575, 72L10936-1575,-

72L10937-1575 .

81F32007-1582-11 HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 212 F Temp: 212*F Continuous Continuous N/A N/A QUALIFICATION REPORT: WCAP 8754 (MCM-1318.00-0026) and Duke analyses (MCC-1381.05-00-0101, MCC-1381.05-00-0102)

METHOD: Test and Analysis EPSR

McGUIRE NUCLEAR STATION - UNITS'1 AND 2 Page 6

-SUMMAni 0F ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Ground Water Drain ' MANUFACTURER: Reliance MODEL #: 2Y-273734 Sump Pump Motors HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN ' DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

This equipment is not required to function for HELBs that affect its environment.

) QUALIFICATION REPORT: Duke Report MDS/PDG-77-1, Calculation MCC-1206.47-00-0001 4

METHOD: Analysis EPSR i

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 7

SUMMARY

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

. EQUIPMENT ID: Component Cooling MANUFACIURER: Westinghouse, MODEL #: 72F44689-1574, 72F44689-Pump Motors and Spares Buffalo 2S74, 72F44689-3S74,

. 72F44689-4574, 72F44690-IS74, 72F44690-2574, 72F44690-3S74, 72F44690-4S74 81F32006-1582-11 HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

^

Temp: 212 F Temp: 212 F Continuous Continuous N/A N/A 1

j QUALIFICATION REPORT: WCAP 8754 (MCM-1318.00-0026) and Duke analyses (MCC-1381.05-00-0101, MCC-1381.05-00-0102)

METHOD: Test and Analysis EPSR

McGUIRE NUCLEAR STATION - UNITS 1 AND 2~ Page 8

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1

LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Boric Acid Transfer MANUFACTURER: Chempump/ MODEL #: Chempump Model Pump Motors Westinghouse GVH-10K-12H-1$

HELB . ENVIRONMENT OPERABILITY OPERABILITY- ACCURACY ACCURACY ENVIRONMENT TO WHICH _ REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED i

(1) QUALIFIED. HELB (% OF SPAN) (% OF SPAN).

, ENVIRONMENT (2)

This equipment is not required to function for HELBs that affect its environment QUALIFICATION REPORT: Duke Report MDS/PDG-77-1, Calculation MCC-1206.47-00-0001 METHOD: Analysis 4

MEQP

=.

~

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 10 SUltiARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT- Rev. 2 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Fuel Pool Cooling MANUFACTURER: Westinghouse, MODEL #: 72F44649-1574, 72F44649-Pump Motors Buffalo- 2574, 72F44650-1576, 72F44650-2S76 HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 156 F Temp: 156 F Continuous Continuous N/A N/A QUALIFICATION REPORT: WCAP 8754 (MCM-1318.00-0026) and Duke analysis (MCC 1381.05-00-0101)

METHOD: Test and Analysis EPSR

T 1 '*

i -

e

~

-McGUIRE NUCLEAR STATION UNITS 1 AND 2 .Page 11

SUMMARY

OF. ENVIRONMENTAL-QUALIFICATION-0F~ CLASS 1E EQUIPMENT Rev.El

. LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT:

EQUIPMENT ID: Residual. Heat Removal MANUFACTURER: Reliance MODEL #i 2YF-882311,' 1YF-882311 Air Handling Unit Motors and Spare HELB ENVIRONMENT OPERABILITY- OPERABILITY- ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED- DEMONSTRATED (1) QUALIFIED HELB .(% 0F SPAN) (% OF SPAN)

ENVIRONMENT (2)

This equipment is not required to function for HELBs that affect its environment QUALIFICATION REPORT: Duke Report MDS/PDG-77-1, Calculation MCC-1206.47-00-0001 METHOD: Analysis EPSR

.m

=.'

.McGUIRE NUCLEAR STATION - UNITS 1 AND 2 . Page 12 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT. Rev. 1

. LOCATED OUTSIDE CONTAINMENT: AND EXPOSED TO HELB ENVIRONMENT 1- :EQUIPPENT ID: Containment Spray . 'MANUFACTORER: Reliance .MODEL #: 1YF-882311 Air Handling Unit Motors and Spare HELB . ENVIRONMENT OPERABILITY OPERABILITY . ACCURACY ACCURACY

ENVIRONMENT. TO WHICH REQUIRED IN DEM0hSTRATED- REQUIRED DEMONSTRATED

(1) -QUALIFIED HELB (% OF SPAN) (% OF SPAN) l ENVIRONMENT (2)

This equipment is not required to function for HELBs that affect its environment 4

4 i

i I -

j QUALIFICATION REPORT: Duke Report MDS/PDG-77-1, Calculation MCC-1206.47-00-0001 l

}

j METHOD: Analysis k.

1 EPSR i

'- " '* ** .~

, .r ;

_. . e,

'McGUIRE NUCLEAR STATI0h -UNITS 1 AND 2- Page 13i-SUMARY- 0F. ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT .. Rev. l' LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO !!ELB ENVIRONMENT-EQUIPMENT ID: . Fuel Pool Air Handling MANUFACTURER: Reliance. MODEL #: 3YF-882311, 1YF-882311 Unit Fan Motors and Spare HELB ENVIRONMENT.' OPERABILITY . OPERABILITY ACCURACY ACCURACY..

ENVIRONMENT TO WHICH REQUIRED IN . DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

. ENVIRONMENT (2)

Temp: 156 F Temp: 156 F Continuous Continuous N/A N/A

}

4 i

QUALIFICATION REPORT: Thermal Life Analysis (MCC-1381.05-00-0127)

I j METHOD: Analysis

?

4 i EPSR s

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 15

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Annulus Ventilation Damper MANUFACTURER: Rotorm HODEL #: 7A Actuators HELB. ENVIRONMENT OPERABILITY OPERABILITY- ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED. REQUIRED DEMONSTRATED (1) -

QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

This equipment is not required to function for HELBs that affect its environment QUALIFICATION REPORT: Duke Report MDS/PDG-77-1, Calculation MCC-1206.47-00-0001 METHOD: Analysis MDSS

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 .Page 16

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT. Rev. 1-LOCATED OUTSIDE' CONTAINMENT AND EXPOSED TO HELB. ENVIRONMENT i

EQUIPMENT ID: Annulus Ventilation Fan Motors- MANUFACTURER: Joy / Reliance MODEL #: 2YF-273608 HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY

ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED

, (1).

QUALIFIED HELB (% OF SPAN). (% OF SPAN)

ENVIRONMENT (2)'

?

f This equipment is not required to function for HELBs that affect its environment.

(

l l

i QUALIFICATION REPORT: Duke Report MDS/PDG-77-1, Calculation MCC-1206.47-00-0001 METHOD: Analysis g

I l

MDSS

~

McGUIRE NUCLEAR STATION'- UNITS;l AND 2 Page 16a-

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF. CLASS 1E EQUIPMENT- Rev. 0 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: ' Annulus Ventilation MANUFACTURER: Farr :MODEL #: N/A Filter Unit Preheater and Controls t

HELB ENVIRONMENT ' OPERABILITY OPERABILITY ACCURACY ACCURACY' ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED. REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) .(% OF SPAN)

ENVIRONMENT (2)

. This equipment is not required to function for HELBs that affect its environment.

i i

i I

QUALIFICATION REPORT: Duke Report MDS/PDG-77-1, Calculation MCC-1206.47-00-0001 l

METHOD: Analysis i

MDSS i

L 1 :-

~

McGUIRE-NUCLEAR STATION'--UNITS 1 AND 2; Page 17-4

SUMMARY

.0F. ENVIRONMENTAL QUALIFICATION OF CLASS'1E. EQUIPMENT :Rev. 1-

-LOCATED OUTSIDE CONTAINMENT AND. EXPOSED TO HELB ENVIRONMENT 4

l EQUIPMENT ID: Aux. Bldg. Filtered Exhaust Fan

. MANUFACTURER: Powers 'MODEL #: N/A Control Panel ABFXF-CP-1A, 1B, 2A, 4

& 2B

'HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY-

. ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED.

(1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

! This equipment is not required to function for HELBs that affect its environment i

)

i i

i

QUALIFICATION REPORT: Duke Report HDS/PDG-77-1, Calculation MCC-1206.47-00-0001 i HETHOD: Analysis i

4 4

MOSS

i

-Page 18 McGUIRE NUCLEAR STATION - UNITS 1 AND 2

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED-0UTSIDE CONTAINMENT'AND EXPOSED TO HELB ENVIRONMENTJ EQUIPMENT ID: Firestat (temperature switch) MANUFACTURER: United Electric. MODEL1: 800G-6CS HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)-

ENVIRONMENT (2).

i a

i This equipment is not required to function fer HELBs.that affect its environment i

)

l QUALIFICATION REPORT: Duke Report MDS/PDG-77-1, Calculation MCC-1206.47-00-0001 l METHOD: Analysis j

s a

MDSS

e

~

. McGUIRE NUCLEAR STATION c- UNITS 1 AND 2 Page 19

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT: 'Rev. 1 LOCATED OUTSIDE CONTAINMENT,AND EXPOSED..T0 HELB ENVIRONMENT l

EQUIPMENT ID: ! Aux. Bldg.; Filtered Exhaust Fan MANUFACTURER: Reliance MODEL #: 1YF-882811, 1YF-882812-3 Motors and Spares 1YF-882900, 1YF-882901 HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT- TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED l (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN).

i ENVIRONMENT (2).

d l This equipment is not required to function for HELBs that affect its environment i

i l

i QUALIFICATION REPORT: Duke Report MDS/PDG-77-1, Calculation MCC-1206.47-00-0001 1

i 3

METHOD: Analysis i

i EPSR

.f 4

McGUIRE NUCLEAR STATION , UNITS 1 AND 2. Page 20

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev., 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED T0 HELB ENVIRONMENT

. EQUIPMENT ID: AHU Differential Pressure MANUFACTURER: Solon Mfg. Co. MODEL #: 7PSIDW.

Switches 4

HELB ENVIRONMENT OPERABILITY -

'0PERABILITY ACCURACY ACCURACY 4 ENVIRONMENT. TO WHICH REQUIRED IN DEMONSTRATED REQUIRED .

DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN)- (% OF SPAN)

. ENVIRONMENT (2)

This equipment is' not required to function for HELBs that affect its environment i

i i

i 4

QUALIFICATION REPORT: Duke Report MDS/PDG-77-1, Calculation MCC-1206.47-00-0001 1 -

METHOD: Analysis i

)

MDSS

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 21

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: ~ Valve Motor Operators MANUFACTURER: Limitorque MODEL #: SMB Order Numbers:

375826-A, 375834-A, 4

375829-A, 375835-A 375831-A, 379664-8 375832-A, 379857-A 375833-A

HELB ENVIRONMENT OFERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRE 0' DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

, ENVIRONMENT (2)

Temp: 212 F Temp: 250 F Continuous Continuous N/A N/A QUALIFICATION REPORT: Limitorque Test Report: B0058, Appendix D, 1/11/80 (MCM-1205.34-0002)

HETHOD: Test MEQP

V McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 22

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 2 LOCATED'0UTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Valve Motor Operators MANUFACTURER: Limitorque MODEL #: SMB Order Numbers:

. (Doghouse) 383584-A & 391179-A, -B 4

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY.

ENVIRONMENT TO WHICH REQUIRED IN DEMONSTPATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (%-OF SPAN) (% OF SPAN).

ENVIROF'HENT(2)

Temp: 300 F* Temp: 340 F 3.77 min. 5.9 min. N/A N/A l

Doghouse environment at time safety function completed - Ref. MCC-1381.05-00-0156.

QUALIFICATION REPORl: Limitorque Test Report: B0058, Appendix B, 1/11/80 (MDM-1205.34-0002)

METHOD: Test l

MEQP

. . ~ .

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 'Page.22a

SUMMARY

0F ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 2 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Valve Motor Operators MANUFACTURER: Limitorque MODEL #: SMB Order Numbers:

383584-A &.391179-A, -B HELB ENVIRONMENT- OPERABILITY OPERABILITY ACCURACY ACCURACY-ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED DEMONSTRATED REQUIRED i

(1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Terp: 212 F Temp: 340 F Continuous Continuous N/A N/A i

i QUALIFICATION REPORT: Limitorque Test Report: 80058, Appendix B, 1/11/80 (MDM-1205.34-0002)

METHOD: Test l

l l MEQP

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 23

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev.11~

LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT'

. EQUIPMENT ID: Valve Motor Operators MANUFACTURER: Rotork MODEL #: NA-2 HELB ENVIRONMENT- OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 212 F Temp: 163 F N/A N/A (Note 3) One reposition One reposition

! =

i QUALIFICATION REPORT: Rotork Test Reports N11/4, December 1970; TR116, October 1973: TR222, June 1975; TR3025, April 1980

. (MCM-1205.34-0001), Rotork Test Report 3059 (MCM-1205.34-1)

METHOD: Test MEQP

McGUIRE' NUCLEAR STATION.- UNITS 1 AND 2 Page 24 SlM4ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS.1E EQUIPMENT- .Rev. 2 LOCATED OUTSIDE CONTAINMENT AND EXPOSED T0 HELB ENVIRONMENT

EQUIPMENT ID: Valve Motor Operators MANUFACTURER: Rotork MODEL #: NA-1 (Doghouse) (S/N < B-4800)

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY i

ENVIRONMENT TO WHICH REQUIRED IN -DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN).

ENVIRONMENT (2)

Temp: '300 F* Temp: 340 F 3.77 min. 5.9 min. N/A N/A i

Doghouse environment at time safety function completed - Ref. MCC-1381.05-00-0156.

i QUALIFICATION REFORT: Rotork Test Reports N11/4, December 1970; TR116, October 1973; TR222, June 1975 (MCM-1205.34-0001)

' METHOD: Test

! MEQP

?.

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 24a.

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 2 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Valve Motor Operators MANUFACTURER: Rotork MODEL #: NA-l' (S/N < B-4800)

HELB ENVIRONMENT 0PERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED

(1)

QUALIFIED HELB (% OF SPAN)' (% 0F SPAN).

ENVIRONMENT (2)

Temp: 212 F Temp: 340 F Continuous Continuous N/A N/A QUALIFICATION REPORT: Rotork Test Reports N11/4, December 1970; TR116, October 1973; TR222, June 1975 (MCM-1205.34-0001)

METHOD: Test HEQP

McGUIRE NUCLEAR STATION - UNITS.1 AND 2 Page 24b

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT . .Rev. 2 4

LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Valve Motor Operators MANUFACTURER: Rotork MODEL 1: NA-1

(Doghouse) (S/N > B-4800) i HELB' ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT T0 WHICH REQUIRED IN DEMONSTRATED DEMONSTRATED i REQUIRED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2) 1

Temp: 300 F* Temp: 385 F 3.77 min. 7.2 min. N/A N/A l

l

Doghouse environment at time safety function completed - Ref. MCC-1381.05-00-0156.

QUALIFICATION REPORT: y 43979-1, Rev. A, dated 12/19/78 (MCM-1205.34-0010)

W'le I

f METHOD: Test l

MEQP 1

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 24c i-

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT _ Rev. 2 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TG HELB ENVIRONMENT EQUIPMENT ID: Valve Motor Operators MANUFACTURER: Rotork MODEL #: NA-1 (S/N > B-4800)

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2) i Temp: 212 F Temp: 385 F Continuous Continuous N/A N/A i

QUALIFICATION REPORT: y 43979-1, Rev. A, dated 12/19/78 (MCM-1205.34-0010)

W'le METHOD: Test 4

I MEQP

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 25

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 2 LOCATED OUTSIDE CONTAINMENT AND' EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Valve Solenoid Operators. MANUFACTURER: Valcor MODEL #: V70900-21-3, V70900-21-l' (Doghouse)

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED

-ENVIRONMENT.

(1) QUALIFIED HELB (% OF SPAN) (% OF SPAN) q ENVIRONMENY(2)

Temp: 300 F* Temp: 346*F 2.57 min. 6.0 min. N/A N/A

Doghouse environment at time safety function completed - Ref. MCC-1381.05-00-0156.

QUALIFICATION REPORT: Test Reports QR70900-21-1 Rev. A (MCM-1210.04-0118); QR52600-515 Rev. B (MCM-1210.04-0115);

MR70905-21-3-1 (MCM-1210.0119)

METHOD: Test & Similarity MPIC

_ .(

1 McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 25a SUPMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 2 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT.

EQUIPMENT ID: Valve Solenoid Operators MANUFACTURER: Valcor MODEL #: V70900-21-3, V70900-21-1 i

HELB ENVIRONMENT- OPERABILITY ~0PERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1)- QUALIFIED- HELB (% 0F SPAN) (% OF SPAN)

ENVIRONMENT (2) l l Terrp: 330 F Temp: 346*F Continuous Continuous N/A N/A l

QUALIFICATION REPORT: Test Reports QR70900-21-1 Rev. A (MCM-1210.04-0118); QR52600-515 Rev. B (MCM-1210.04-0115);

MR70905-21-3-1 (MCM-1210.0119)

METH00: Test & Similarity MPIC

(

s.

. fu McGUIRE NUCLEAR STATION - UNITS'-1 AND 2 Page;26:

- SUMARY OF ENVIRONMENTAL Q'JALIFICATION OF CLASS 1E EQUIPMENT. : Rev. ;. 2 LOCATED OUTSIDE-CONTAIN'4ENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: : Valve Solenoid Operators MANilFACTURER: 6S00 MODEL'i: .'NPL 8316E34E, NP 8316E36E-

-(Doghouse) i

! . HELB ENVIRONMENT OPERABILITY OPERABILITY ~ ACCURACY ' ACCURACY' 4

ENVIRONMENT :TO:WHICH . REQUIkED IN ' DEMONSTRATED DEMONSTRATED REQUIRED (1) . QUALIFIED. HELB (% OF SPAN) (% OF SPAN)

! ENVIRONMENT (2)

.Terp: 325 F* Temp: 346 F 5.6 min. 6.0 min. N/A N/A' ,

Doghouse environment at time safety function' completed - Ref. MCC-1381.05-00-0156.

j QUALIFICATION REPORT: Test Report: AQS21678/TR (MCM-1210.04-0117) i h METHOD: Test i

4 I

MPIC l

i I .

'\;

~

~

McGUIRE NUCLEAR STATION -' UNITS'1 AND 2 Page 26a'~

i

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF~ CLASS 1E EQUIPMENT- Rev. 2

. LOCATED OUTSIDE CONTAINMENT AND EXPOSED:TO HELB ENVIRONMENT CQUIPMENTLID: Valve Solenoid Operators. MANUFACTURER: ASCO MODEL #: NP 8316E34E, NP 8316E36EL i HELB ENVIRONMENT .0PERABILITY- '0PERABILITY ACCURACY ACCURACY.

ENVIRONMENT TO WHICH REQUIRED IN "EMONSTRATED REQUIRED DEMONSTRAIED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN) j ENVIRONMENT (2)

Temp: 330 F Temp: 346 F Continuous Continuous N/A N/A 9

QUALIFICATION REPORT: Test Report: AQS21678/TR (MCM-1210.04-0117) 4 METil00: Test ,

I MPIC l

~

t McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 27 SUMARY'0F ENVIRONMENTAL QUALIFICATION OF CLASS 1E~ EQUIPMENT - Rev. 2.

LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENTID: Valve Operator - MSIV ' MANUFACTURER: Atwood & Morrill' MODEL #: 34" MSIV w/ Chicago Fluid (Doghouse) Pwr. actuator 4

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HEL8 (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 325 F* Temp: 340 F 5.6 min. 5.9 min. N/A N/A j j

, CDoghouse environment at time safety function completed - Ref. MCC-1381.05-00-0156.

i t

QUALIFICATION REPORT: Test Report Procedure No. 20139500 dated 5/1/79 (MCM-1205.34-0005)

METHOD: Test 4

l MEQP l

.ng . -

~,

~ '

"4 fil

;y 7* r ..

McGUIRE NUCLEAR STATION - UNITS 1 AND 2- Page:28:

SUMARY OF- ENVIRONf1 ENTAL-QUALIFICATION 0F CLASS 1E EQUIPMENT. Rev. 1-LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT-EQUIPMENT ID: Valve Solenoid' Operators -MANUFACTURER: Valcor MODEL #: V526', V573 .

('

HELB -ENVIRONMENT '0PERABILITY OPERABILITY . ACCURACY ACCURACY.

l ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED' DEMONSTRATED i (1). QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2) i Temp: 212 F Temp: 346 F Continuous Continuous N/A N/A' QUALIFICATION REPORT: Test Report QR-52600-5940-2, July 5, 1979 (MCM-1205.34-0012) ;

l METHOD: Test i

HEQP

- ~

n-

,- :L

?. -

1 *,

-McGUIRE NUCLEAR STATION:- UNITS 1-AND 2 Page 29'

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 2 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT-EQUIPMENT-ID: Valve Operator FWIV MANUFACTURER: Borg Warner' MODEL #: 12" Gate w/ Elect Hyd.

(Doghouse) (Unit 1) 0per.

NVD F/N 36310.

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY.

ENVIRONMENT TO WHICH . REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED.

-(1) QUALIFIED .

HELB (% OF SPAN) (% OF SPAN)

~ ENVIRONMENT (2)

Terap: 300 F* Temp: 330*F 2.57 min. 5.9 min. N/A N/A (Note 4)

Doghouse environment at time safety fonction completed - Ref. MCC-1381.05-00-0156.

QUALIFICATION REPORT: Test. Report Nos. 1785 & 1779, dated 11/12/79 (MCM-1205.34-0006)

METHOD: Test MEQP

( n 1

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 29a

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 2 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Valve Operator FWIV MANUFACTURER: .Borg. Warner MODEL #: 12" Gate w/ Elect Hyd.

(Doghouse) (Unit 2) Oper.

NVD P/N 88500 I

HELB ENVIRONMENT OPERABILITY 0PERABILITY ' ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 300 F* Temp: 345 F 2.57 rin. 6.0 min. N/A N/A (Note 4)

Doghouse environment at time safety function completed - Ref. MCC-1381.05-00-0156.

QUALIFICATION REPORT: Test Report No. 1989, dated 05/18/83 METHOD: Test MEQP

4

~*

McGUIRE NUCLEAR STATION - UNITS'1'AND 2 Page 30

SUMMARY

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

. EQUIPMENT ID: Level Switch (Groundwater MANUFACTURER: Robertshaw . MODEL #: SL-402-84-3 Drainage Sump C Level)

HELB ' ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB- (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

This equipment is- not required to function for HELBs that affect its environment.

QUALIFICATION REPORT: Duke Report MDS/PDG-77-1, Calculation MCC-1206.47-00-0001 METHOD: Analysis MPIC

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 . Page 30a ~

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 2 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Level Switch MANUFACTURER: Magnetrol MODEL~#: A103F-3X-Y-MPG-TDM-(Doghouse) S1M04DC-SIMD4DC-SIMD4DC HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY. ACCURACY ENVIRONMENT TO WHIu.. REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Tcmp: 240 F Temp:285 F 15 seconds Continuous 10.25" 0.25" following a main feedwater line break QUALIFICATION REPORT: Duke QTF Report TR-053 and TR-060.

METHOD: Test MPIC

r. . _ _ _ _ . . _ _ - - . ._

P .'

McGUIRE'NUCLEARSTATION-UNITSiAND2 Page 31 Sum ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT' Rev. 2 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT' EQUIPMENT ID: Stem Mounted Limit Switches MANUFACTURER: NAMC0 MODEL #: .EA180, EA740 (Doghouse)

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 300 F* Temp: 340 F 2.57 min. 5.9 min. N/A N/A l

CDoghouse environment at time safety function completed - Ref. MCC-1381.05-00-0156.

QUALIFICATION REPORT: NAMC0 Test Report QTR-106 dated 9/2/81 (MCM-1205.34-0009) and .

NAMCO Test Report-QTR-111, Rev. O dated 10/01/81 (MCM-1205.34-0008)

METHOD: Test MEQP

McGUIRE NUCLEAR STATION - UNITS l'AND 2 'Page 31a SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT - Rev. 2 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Stem Mounted Limit Switches MANUFACTURER: NAMCO. MODEL #: EA180, EA740 HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY- ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED 1

(1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 212 F Temp: 340 F Continuous ' Continuous N/A N/A i

QUALIFICATION REPORT: Nail:0 Test Report QTR-106 dated 9/2/81 (MCM-1205.34-0009) and NAMC0 Test Report QTR-111, Rev. O dated 10/01/81 (IICM-1205.34-0008)

METHOD: Test HEQP

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 32

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXI 0 SED TO HELB ENVIRONMENT EQUIPMENT ID: Stem Mounted Limit Switches MANUFACTURER: NAMC0 MODEL #: EA-170-302 HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT T0 WHICH : REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 212 F. Temp: 248 F Continuous Continuous N/A N/A l

J

f QUALIFICATION REPORT: NAMC0 Test Report QTR-107 dated 3/11/81 (MCM-1205.34-0011) '

, METHOD: Test j MEQP

. p, '

ll McGUTPE' NUCLEAR STATION - UNITS 1'AND 2 Page 33

SUMMARY

GF ENVIRONMENTAL QUALIFICATION OF CLASS IE EQLIPMENT .Rev. 2-LOCATED OUTSIDE CONTAINMENT AND EXPOSED'TO HELB ENVIRONMENT

EQUIPMENT ID: Cable - Control MANUFACTURER: Brand Rex MODEL.#: XLPE Insulation (Procurement (Doghouse) Specs: MCS-1354.02-4, 5, 7 &-

& 9 & MCS-1354.04-14)

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED i (1) QUALIFIED HELB (% OF SPAN)' (% OF SPAN) j ENVIRONMENT (2)

Temp: 325 F Temp: 346*F _5.6 min. 6.0 min. N/A N/A i

i

Doghouse environment at time safety function completed - Ref. MCC-1381.05-00-0156.

}

I i

QUALIFICATION REPORT: Test Reports FC4113 (MCM-1354.00-0007) FC5120-1 (MCM-1354.00-0023) and FC5120-3 (MCM-1354.00-0024) j j METHOD: Test l

}

i EPSS

r

~

McGUIRE NUCLEAR STATION - UNITS 1 AND 2- Page 33a

SUMARY OF. ENVIRONMENTAL-QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 2 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT-EQUIPMENT ID: ' Cable - Control MANUFACTURER: Brand Rex MODEL #: XLPE_ Insulation (Procurement Specs: MCS-1354.02-4, 5, 7 &

& 9 & MCS-1354.04-14)

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY-

ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2) ,

i i

)- Temp: 330 F Temp: 346 F Continuous Continuous N/A N/A ,

l (Note 6) ,

i l

I

. QUALIFICATION REPORT: Test Reports FC4113 (McH-1354.00-0007) FC5120-1 (HCM-1354.00-0023) and FC5120-3 (MCM-1354.00-0024) i HETH00: Test

.i I

l EPSS i

~

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 . Page 34.

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF' CLASS 1E EQUIPMENT- -Rev. 2 LOCATED OUTSIDE CONTAINMENT AND-EXPOSED T0 HELB ENVIRONMENT EQUIPMENT ID: Cable - Instrumentation MANUFACTURER: 'Eaton (Samuel Moore) MODEL #: .EP/Hypalon Insulation.

(Doghouse) (Procurement Specs:

MCS-1354.03-1, 2, 3 & 5 &

MCS-1354.04-2 & 5)

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN)- (% OF~ SPAN)

ENVIRONMENT (2)

Tamp: 325 F* . Temp: 340 F 5.6 min. 5.9 min. N/A N/A

0oghouse environment at time safety function completed - Ref. MCC-1381.05-00-0156.

QUALIFICATION REPORT: Test Report F-C3683 (MCM-1354.00-0006)

METHOD: Test EPSS

~ 7, -

Y

<i McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page'34a

SUMMARY

OF ENVIRONMENTAL. QUALIFICATION OF CLASS'1E EQUIPMENT Rev. 2 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Cable - Instrumentation MANUFACTURER: 'Eaton (Samuel Moore) MODEL #: .EP/Hypalon Insulation (Procurement Specs:

MCS-1354.03-1, 2, 3 & 5 &

MCS-1354.04-2 & 5) ,

HELB ENVIRONMENT OPERABILITY . 0PERABILITY 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-03683 (MCM-1354.00-0006)

METHOD: Test EPSS

.a

" ~

y,..,

~

,~.8

-McGUIRE NUCLEAR: STATION - UNITS 1-ANDL2, Page 35' SUM 4ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT- Rev. 2 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Cable - Control, Instrumentation, MANUFACTURER: Okonite MODEl l: EP,EP/Hypalon,&'Hypalon and Power- Insulation.(Procurement

.(Doghouse) Specs: MCS-1354.01-1,-2 &-

MC5-1354.02-4, 6, 9 &.~

MCS-1354.03-4)

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY . ACCURACY.

ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED' (1) QUALIFIED HELB (% OF SPAN) (% 0F SPAN)

ENVIRONMENT (2)

Temp: 325 F Temp: 340 F 5.6 min. 5.9 min. N/A N/A-(Note 6)

Doghause environment at time safety function completed - Ref. MCC-1381.05-00-0156.

QUALIFICATION REPORT: Test Reports N1, May 2, 1975 (MCM-1354.00-0010); FN-1, July 3, 1978 (MCM-1354.00-0013); G-3, June 28, 1979 (MCM-1354.00-0012; 110E, November 12,1970;(MCM-1354.00-0016); Duke Test Report TR032, November 5, 1982 (MCM-1354.00-0022); G1,. February 17, 1976 (MCM-1354.00-0045)

METHOD: Test i

EPSS

r

McGUIRE NUCLEAR STATION ~- UNITS 1 AND 2 . Page 35a SUPMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT. .Rev. 2 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB. ENVIRONMENT EQUIPMENT ID: Cable - Control, Instrumentation, MANUFACTURER: Okonite MODEL #: EP, EP/Hypalon, & Hypalon

-and Power . Insulation (Procurement

. Specs: MCS-1354.01-1, 2 &

MCS-1354.02-4, 6, 9 &

MCS-1354.03-4)

HELB ENVIRONMENT OPERABILITY 0PERABILITY ACCURACY ACCURACY ENVIRONMEN1 TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 33fF Temp: 340 F Continuous Continuous N/A- N/A (Note 6)

QUALIFICATION REPORT: Test Reports N1,-May 2, 1975 (MCM-1354.00-0010); FN-1, July 3, 1978 (MCM-1354.00-0013); G-3, June 28, 1979 (MCM-1354.00-0012; U 0E,ILvember 12, 1970 (MCM-1354.00-0016); Duke Test Report TR032, Novembar 5, 1982 (MCM-1354.00-0022); G1, February 17, 1976 (MCM-1354.00-0045)

METHOD: Test EPSS

- a

u. i McGUIRE NUCLEAR STATION'- UNITS 1 AND 2 'Page 36 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT 'Rev. 2 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: . Cable.- Control MANUFACTURER: Okonite MODEL #: Tefzel 280 Insulation ,

(Doghouse) (Procurement Spec-MCS-1354.04-6)

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN . DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 325 F . Temp: 341 F 5.6 min. 5.9 min. N/A N/A

Doghouse environment at time safety flinction completed - Ref. MCC-1381.05-00-0156.

l QUALIFICATION REPORT: Test Report K-0-1, September 1979 (MCM-1354.00-0011), and K-8-1, April 4, 1981 (MCM-1354.00-0044)

METHOD: Test EPSS

4 McGUIRE NUCLEAR STATION - UNITS 1 AND 2 . Page-36a SUMARY 0F ENVIRONMENTAL-QUALIFICATION'0F CLASS '1E EQblPMENT Rev. 2 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Cable - Control MANUFACTURER: Okonite MODEL #: Tefzel 280 Insulation (Procurement S MCS-1354.04-6)pec:

i .

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: 341 F Continuous Continuous N/A N/A 1

(Note 6) i i

l QUALIFICATION REPORT: Test Report K-0-1, September 1979 (MCM-1354.00-0011), and K-8-1, April 4, 1981 (MCM-1354.00-0044) i i

1 l METHOD: Test 1

l EPSS

q

~

13-McGUIRE NUCLEAR STATION - UNITS 1 AND 2' Page 37

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 2

,, LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Cable - Control and Power. MANUFACTURER: Anaconda MODEL #: EP Insulation and (Doghouse) EP/Hypalon Insulation (Procurement Specs:

MCS-1354.01-2 & 4, &

MCS-1354.02-3, 6 & 9 HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN- DEMONSTRATED REQUIRED . DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

, Temp: 325 F Temp: 346 F 5.6 min. 6.0 min. N/A 'N/A CDoghouse environment at time safety function completed - Ref. MCC-1381.05-00-0156.

j QUALIFICATION REPORT: Test Reports F-C4350-2 (MCM-1354.00-0008) and F-C4350-3 and Supplement (MCM-1354.00-0009)

.i '

l METHOD: Test i

j li EPSS .

.p -.

x., -

[ . . .j McGUIRE NUCLEAR STATION . UNITS 1 AND 2 -Page 37a

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 2 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Cable - Control and Power MANUFACTURER: Anaconda MODEL #: 'EP Insulation'and EP/Hypalon Insulation (Procurement Specs:

MCS-1354.01-2 & 4, &

. MCS-1354.02-3, 6 & 9 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: 346*F Continuous Continuous N/A N/A (Note 6)

QUALIFICATION REPORT: Test Reports F-C4350-2 (MCM-1354.00-0008) and F-C4350-3 and Supplement (MCM-1354.00-0009)

METHOD: Test EPSS

~

f tL McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 38

SUMMARY

OF ENVIRONMENTAL-QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Remote Starter INIA &.1 NIB MANUFACTURER: Westinghouse MODEL #: A201 J3CA-HELB ENVIRONMENT OPERABILITY OPERABILITY . ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED . . DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

This equipment is not required to function for HELBs that affect its environment i

QUALIFICATION REPORT: Duke Report MDS/PDG-77-1, Calculation MCC-1206.47-00-0001 j METHOD: Analysis i

' F EPSA

McGUIRE NUCLEAR STATION - UNITS'1 AND 2 Page 39 SUMr1ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSEC TO HELB ENVIRONMENT EQUIPMENT ID: Contactor 1FW27A MANUFACTURER: Westinghouse MODEL #: A201 J3CA HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED.IN DEMONSTRATED DEMONSTRATED REQUIRED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

This equipment is not required to function for HELBs that affect its environment QUALIFICATION REPORT: Duke Report MDS/PDG-77-1, Calculation MCC-1206.47-00-0001 METHOD: Analysis EPSA

.3;.

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 .Page 40 '

'SUPMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1-

= LOCATED OUTSIDE CONTAINMENT AND EXPOSED T0 HELB ENVIRONMENT EQUIPME.iT ID: Current / Voltage Alarm MANUFACTURER: RIS .MODEL'#: ET1215

-(Note 7) l HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ' ACCURACY

{ ENVIRONMENT TO WHICH REQUIRED IN . DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED -HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 132.4 F Temp: 140*F Continuous Continuous i 2.5% 1 0.5%

(worst case) ,

l I

i i

QUALIFICATION REPORT: RIS Specification (ESSEM V-A-4) j METHOD: Analysis

! ECSE-i

~ C;.;

.McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 41 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Fuse MANUFACTURER: Bussmann MODEL #: FNA (Note 7)

HELB ENVIRONMENT OPERABILITY OPERABILITY ' ACCURACY. ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) -QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Te:p: 212 F 212 F Continuous Continuous N/A N/A (worst case) (Note 8)

QUALIFICATION REPORT: Bussmann Derating Curve (ESSEM III-A-4) -

METHOD: Analysis ECSE

~

a p

~

. ; t,

-McGUIRE NUCLEAR STATION . UNITS 1 AND 2 Page 42 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS '1E EQUIPMENT- Rev. l LOCATED OUTSIDE CONTAINMENT AND EXPOSED.TO HElB ENVIRONMENT.-

EQUIPMENT.ID: Fuse MANUFACTURER: Bussmann MODEL #: KTK.

-(Note.7) .

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ~ ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED . REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) . (% OF SPAN)

ENVIRONMENT (2)

Temp:. 212 F 212 F Continuous Continuous N/A N/A (w::rst case) (Note 8).

QUALIFICATION REPORT: Bussman Derating Curve (ESSEM III-A-1)

METHOD: Analysis ECSE

. s[

=

.McGUIRE' NUCLEAR-STATION - UNITS 1 AND 2 I Page 43

SUMMARY

OF onVIRONMENTAL QUALIFICATION OF: CLASS 1E. EQUIPMENT Rev.~1 LOCATED OUTSIDE. CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT

! EQUIPMENT ID: Fuse block MANUFACTURER: 'Bussmann MODEL #: 3792 (Note 7) 4 HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY . ACCURACY ENVIRONMENT TO WHICH REQUIRED IN- DEM0dSTRATED REQUIRED DEMONSTRATEDn (1) QUALIFIED -HELB .(% OF SPAN) (% 0F SPAN)

ENVIRONMENT (2)

Iemp: 212 F ' Temp: 250 F1 Continuous Continuous N/A N/A

(worst case) 4 i

i 1

)

~

QUALIFICATION REPORT: Bussmann Manufacturing Report dated 3/13/79 (ESSEM IV-A-1) 1 METHOD: Analysis t

ECSE

McGUIRE NUCLEAR 1 STATION - UNITS 1 AND 2 Page744

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev.-1 LOCATED 0UTSIDE CONTAINMENT AND EXPOS'ED TO HELB ENVIRONMENT-EQUIPMENT ID: Fuse block MANUFACTURER: Bussmann MODEL #: 3839 (Note 7)

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY. ACCURACY ENVIRONMENT 'TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED

, (1) QUALIFIED HELB (% OF SPAN)- (% OF SPAN)

ENVIRONMENT (2) 4 Temp: 212 F . Temp: 250 F Continuous Continuous N/A N/A (worst case) i

QUALIFICATION REPORT: Bussmann Manufacturing Report dated 3/13/79 (ESSEM IV-A-5)

METHOD: Analysis ECSE

. .s

.o J .;

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 .Page 45 j

SUMMARY

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

EQUIPMENT ID: Fuse block MANUFACTURER: Bussmann H0 DEL #: 4439 (Note 7)

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN).

ENVIRONMENT (2)

Temp: 212 F Temp: 250 F Continuous Continuous N/A N/A (worst case) i QUALIFICATION REPORT: Bussmann Manufacturing Report dated 3/13/79 (ESSEM IV-A-2)

ISETHOD: Analysis ECSE.

..q y

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 . Page 46 1

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS'1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT !

EQUIPMENT ID: Indicating Light- MANUFACTURER: Cutler-Hammer - MODEL #: E29 (Note 7)

HELB ENVIRONMENi~ 0PERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN- DEMONSTRATED REQUIRED ' DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 200 F ' Temp: 255*F Continuvis Continuous N/A- N/A (worst case)

QUALIFICATION REPORT: Duke QTF Report TR-010 (MCM-1393.02-0003, ESSEM III-B-1) ,

METHOD: Test ,

ECSE l

a y,

, Ci l

.i McGUIRE NUCLEAR STATION - UNITS'1 AND'2' lPage47

.SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT- Rev. 1 LOCATED OUTSIDE CONTAINMENT.AND EXPOSED TO HELB ENVIRONMENT-

. EQUIPMENT ID: Optical Isolator MANUFACTURER: E-Max MODEL #: 1750127 (Note 7) 1750126 HELB ENVIRONMENT OPERABILITY- OPERABILITY' ACCURACY' ACCURACY-ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Te:p: 132.4 F . Temp: 223 F . Continuous Continuous N/A N/A (worst case) (Note 9) (Note 9)

QUALIFICATION REPORT: Duke QTF Report TR-055 (CNM-1338.00-00-0034)

METHOD: Test ECSE

4, :.

~

McGUIRE NUCLEAR STATION.- UNITS 1 AND 2 . Page 48

SUMMARY

OF ENVIRONMENTAL' QUALIFICATION OF CLASS 1E. EQUIPMENT' Rev.:1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED.T0 HELB ENVIRONMENT.

EQUIPMENT ID: Fuse block ' MANUFACTURER: Bussmann MODEL #: 2807'and 2808 (Note 7)

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY' ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED' (1) -QUALIFIED HELB (% OF SPAN) -(% OF SPAN)

ENVIRONMENT (2)-

Temp: 212 F Temp: 250*F Continuous Continuous N/A N/A' 1 (worst case)

QUALIFICATION REPORT: Bussmann Manufactu.-ing Report d6ted 3/13/79 (ESSEM IV-A-11)

METHOD: Analysis ECSE

?, -

McGUIRE-NUCLEAR STATION - UNITS 1 AND'2 Page149'.

SUMMARY

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

EQUIPMENT ID: Fuse block MANUFACTURER: Bussmann MODEL #: '4575 (Note 7)

HELB ENVIRONMENT OPERABILITY OriRABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN ' DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB -

(% OF SPAN) -(% OF SPAN)

ENVIRONMENT (2) t

Temp: 212 F Temp: 250 F Continuous Continuous N/A N/A l (worst case) l I

4 j QUALIFICATION REPORT: Bussmann Manufacturing Report dated 7/24/80 (ESSEM IV-A-3)

}

METHOD: Analysis 4

i ECSE i

q.

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 50

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT,ID: Power Supply MANUFACTURER: Lambda MODEL #: LCS (Note 7)

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB -(% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 132.4 F Temp: 160 F Continuous Continuous 110% regulation i 1% regulation (worst case) of output voltage of output voltage QUALIFICATION REPORT: Lambda Specification Data (ESSEM VIII-G-1)

METHOD: Analysis ECSE

v McGUIRE NUCLEAR STATION - UNITS 1 AND 2 .

Page 51

Rev. 1 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT.ID: Relay MANUFACTURER: Cutler-Hamer MODEL #: D23 (Note 7)

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH . REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED l (1) QUALIFIED HELB .(% OF SPAN) (% OF SPAN)

ENVIRONMENT (2) 1 j Temp: 212 F Temp: 255 F Continuous Continuous- N/A N/A l (worst case) 1 i

QUALIFICATION REPORT: Duke QTF Report TR-010 ('iCM-1393.02-0003, ESSEM VII-A-2.1)

)

i j METHOD: Test l

l 4

j ECSE-

.c

i;.

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 . Page~52 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT ' Rev. l' LOCATED OUTSIDE CONTAINMENT AND EXPOSED.T0 HELB ENVIRONMENT

-EQUIPMENT ID: Relay MANUFACTURER: Cutler-Hammer M00EL 1: D26 (Note'7) i HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIFONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB -(% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 212 F Ten.p: 255 F Continuous Continuous N/A N/A (worst case)

QUALIFICATION REPORT: Duke QTF Report TR-010 (MCM-1393.02-0003, ESSEM.VII-A-2.2)'

METHOD: Test ECSE

~

w. '

[

'- e ,1

. . ll a

McGUIRE. NUCLEAR STATION - DNITS 1-AND 2 -Page 53

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 .

LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Relay MANUFACTURER: Struthers-Dunn MODEL #: 219 (Note 7)

HELB ENVIRONMENT OPERABILITY OPERABILITY. ACCURACY ACCURACY ENVIRONMENT TO kHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED -

(1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2) 9 Temp: 212 F Temp: 222*F Continuous Continuous N/A N/A .

(worst case) J l

QUALIFICATION REPORT: McGuire Nuclear Station Pipe Rupture Temperature Component Test (MCM-1393.02-0001, ESSEM VII-A-3)

METHOD: Test / Analysis ECSE

^

.<. :]

/

9 McGUIRE NUCLEAR STATION - UNITS 1 AND 2

Page'54

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev.'1' LOCATED OUTSIDE. CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT-EQUIPMENT ID: Relay - Timing MANUFACTURER: Agastat MODEL #: 7000 Series (Note 7)

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ' - ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED. REQUIRED DEMONSTRATED ;

(1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 130 F Temp: 165*F Continuous Continuous 120% 120%

(worst case)

QUALIFICATION REPORT: Agastat Specification Data (ESSEM VII-C-5)

METHOD: Analysis ECSE

7

7 (

,J McGUIRE NUCLEAR STATION - UNIls 1 AND 2 Page 55 SU M ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Res . 1 -

LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT' L

EQUIPMENT ID: Resistor MANUFACTURER: Ohmite MODEL #: Brown Devil (Note 7)

HELB ENVIRONMENT OPERABILIiY OPERABILITY ACCURACY ACCURAC" ENVIRONMENT TO WHICH . REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRAl'ED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temy: 208 F 208 F Continuous Continuous 13% of resistor 11% of resistor (worst case) (Note 8) value value (Note 10) ,

QUALIFICATION REPORT: Ohmite Derating Curve (ESSEM IX-B-2)

METHOD: Analysis ECSE

q 9 _

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 56 SUMARY OF ENVIROMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED CUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRO WENT EQUIPMENT ID: Surge Suppressor MANUFACTURER: General Semiconductor M00EL 1: Tranzorb (Note 7)

HELB ENVIROMENT -OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB- (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 212 F Temp: 302*F Continuous Continuous N/A N/A (worst case)

QUALIFICATION REPORT: General Semiconductor Specification (ESSEM III-C-1)

HETHOD: Analysis ECSE

5, McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 57 Su m ARY OF ENVIR0 M ENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Resistor MANUFACTURER: Ohmite MODEL #: Dividohm (Note 7)

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 130*F 130 F Continuous Continuous N/A N/A (worst case) (Note 8) l l

QUALIFICATION REPORT: Ohmite Derating Curve (ESSEM IX-B-3)

METHOD: Analysis ECSE

O

- +.

v-McGUIRE NUCLEAR STATION - UNITS l'AND 2 Page 58 SUMARY OF ENVIROMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT.

EQUIPMENT ID: Switch and Indicating Light MANUFACTURER: Cutler-Hammer MODEL'#: E30 (Note 7)

HELB ENVIROK1ENT OPERABILITY OPERABILITY ACCURACY ACCURACY-ENVIRONMENT TO WHICH REQUIRED IN . DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 212*F Temp: 255*F Continuous Continuous N/A N/A (worst case)

QUALIFICATION REPORT: Duke QTF Report TR-610 (MCM-1393.02-0003, ESSEM VI-C-1)

METHOD: Test ECSE

_8

,S

'.3 McGUIRE NUCLEAR STATION - UNITS 1 AND 2 -Page 59 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Selector Switch MANUFACTURER: Cut'.er-Hammer MODEL #: 10250T (Note 7)

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 208 F Temp: 255*F Continuous Continuous N/A N/A (worst case) .

QUALIFICATION REPORT: QTF Report TR-010 (MCM-1393.02-0003, ESSEM VI-A-1 & 4)

METHOD: Test ECSE

, - p

~

s , (s McGUIRE NUCLEAR STATION - UNITS 1 AND 2- '

.Page 60-SUMARY OF ENVIROMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAIMENT' AND EXPOSED 10 HELB ENVIROMENT.

EQUIPMENT ID: Terminal Block

~

MANUFACTURER: States' -MODEL #: ZWM and NT (Note 7)

HELB ENVIROMENT OPERA 8ILITY -OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED . HELB .(% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 212 F Temp: 346*F Continuous Continuous- N/A N/A -

(worst case)

QUALIFICATION REPORT: QTF Report TR-028 (MCM-1393.02-0004, ESSEM IV-B-4 & 5)

METHOD: Test EC3E

c -

McGUIRE' NUCLEAR STATION - UNITS 1 AND'2- Page 61

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E' EQUIPMENT' Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Terminal Block MANUFACTURER: Buchanan MCDEL #: Solid Link SS & TS (Note 7)

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY- ACCURACY ENVIRONMENT T0.WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 208 F Temp: 346*F Continuous Continuous N/A N/A (worst case)

QUALIFICATION REPORT: QTF Report TR-028 (MCM-1393.02-0004, ESSEM IV-B-2 & 3)

METHOD: Test ECSE

c- y 1

~

N McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 62 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT - Rev. 1 LOCATED OUTSIDE_ CONTAINMENT AND EXPOSED T0 HELB ENVIRONMENT EQUIPMENT ID: Terminal Block MANUFACTURER: Stanwick MODEL #: DG & SLS (Note 7)

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED ~

(1) QUALIFIED HElB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 208 F Temp: 346 F Continuous Continuous . N/A N/A (worst case)

QUALIFICATION REPORT: QTF Report TR-028 (MCM-1393.02-0004, ESSEM IV-B-1.1 & 1.2)

METHOD: Test ECSE

y 4

- s McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 63 SUMARY OF ENVIROMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT-EQUIPMENT ID: Signal Transmitter MANUFACTURER: RIS MODEL #: .SC-1302 (Note 7)

HELB ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO MiICH REQUIRED _IN DEMONSTRATED REQUIRED DEMONSTRATED' (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

. ENVIRONMENT (2)

Temp: 130 F Temp: 140 F Continuous Continuous N/A N/A (worst case)

QUALIFICATION REPORT: RIS Specification (MCM-1346.00-0010)

METHOD: Analysis ECSE

s McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 64

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF' CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED-TO HELB ENVIRONMENT EQUIPMENT ID: Fuse . MANUFACTURER: .Littelfuse MODEL #: Normal Blo & Slo-Blo

.(Note 7)

HELB ENVIRONMENT 0PERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED . REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2) .

Temp: 208 F 208* F Continuous Continuous N/A N/A (worst case) (Note 8)

QUALIFICATION REPORT: Littelfuse Derating Curve.(ESSEM III-A-7)

METHOD: Analysis ECSE

~

y-

, T,

.w McGUIRE NUCLEAR STA! ION - UNITS 1 AND 2: ~Page,65L SUMARY OF ENVIR0 MENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 0.

LOCATED OUTSIDE CONTAIMENT AND EXPOSED TO HELB ENVIROMENT EQUIPMENT ID: Leeel Switch - MANUFACTURER: Barton MDDEL #: 288A UHI Water Accumulator

'HELB ENVIRO MENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIROMENT TO WHICH REQUIRED IN DEMDNSTRATED REQUIRED DEMONSTRATED .

(1) QUALIFIED HELB (% OF SPAN) (% OF SPAN):

ENVIRONMENT (2).-

This equipment is not required to function for HELBs that affect its environment.

QUALIFICATION REPORT: Duke Report MDS/PDG-77-1, Calculation MCC-1206.47-00-0001 METHOD: -Analysis ECSE e

p. -

5 s

McGUIRE NUCLE #P 51Ai10N - UNITS 1 AND 2 Page 66 SUMARY OF ENVIROMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT. Rev. 2 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT EQUIPMENT ID: Transmitter - MANUFACTURER: Rosemount. MODEL #: 1153005 Auxiliary Feedwater Flow (Doghouse)

HELB' ENVIROMENT OPERABILITY OPERA 8ILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH . REQUIRE 0 IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED HELB (% OF SPAN) (% OF SPAN)

ENVIROMENT(2)

The Auxiliary Feedwater Flow is not required to mitigate the consequences of a main steam line break in the doghouse.

QUALIFICATION REPORT: N/A METHOD: N/A MPIC

o a

4.

d' McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 66a Su mAkY OF ENVIRONMENTAL _ QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 2 LOCATED OUTSIDE CONTAIMENT AND EXPOSED TO HELB ENVIROMENT EQUIPMENT ID: Transmitter - MANUFACTURER > Rosemount MODEL #: 1153005 Auxiliary Feedwater Flow (Doghouse)

HELB ENVIROMENT OPERA 8ILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO 5MICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1) QUALIFIED .HELB (% OF SPAN) (% OF SPAN)

ENVIRONMENT (2)

Temp: 240*F Temp: 350*F Continuous Continuous 128.13% 128.13%

QUALIFICATION REPORT: Wyle Test Report 45592-1 (MCM-1210.0178) ,

METHOD: Test a

MPIC

- - - - = - - - = - - + - - - - - - - - - ---- = --

, p ,g o i '

Page 3N1 !

r- '

Revisien 2 a

c. i

~

c ,

"i . s MCGUIRE NUCLEAR STATION UNITS 1 AND 2 l

. ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT

i. LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO HELB ENVIRONMENT .

r p Note 1 [

r' :The methods employed to evaluate pipebreaks and to determine'the resulting .

Lenvironmental parameters are discussed in Duke Power Company Report les/POG-77-1. The Evaluation of the Effects of Postulated Pipe Failures i

,Outside Containment for McGuire Nuclear Station.

l Note 2 l

~The pipe rupture environment is assumed to exist for 2 1/2 hours based on 30 minutes.at the peak temperature after which action t,y the operator isolates the break and allows.the Auxiliary Building temperature to decrease to normal ['

in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Use'of the term " Continuous" indicates operability required /

demonstrated throughout the pipe rupture' period, ,

t

," The pipe rupture environmental analysis for the Doghouse was conducted separate- "

ly taking into consideration different, sizes of main steam line breaks. The

<. 1 equipment summary sheet parameters are based on the " worse case" size break ,

l 'with respect to actuation time of the equipment'and the time when the Doghouse temperature' reaches the qualification temperature of the equipment. All equip- '

ment located in the Doghouse is identified under " Equipment 10." ;

9' '

Note 3 1 ~l Rotork Test Report'TR-3025 shows.that when the qualifted 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 i nove to its safety position.. No further safety function is required.

fy . !

Note 4 The test was conducted for 30 minutes ' however, the Class 1E solenolds 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.

i

' Note 5-baleted ,

~

=,

Note 6

'The HEL8 analysis has identified pipe breaks resulting in higher temperatures; {

however, there are no cables exposed to temperatures above 330*F, except in ;

y 'the doghouse which is' addressed separate 1y. ,

8 i

l j

~

j

, e ATTACHMENT 4 ,

SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT !

a P_aje, Rev. M Rev. M Rev.

I 1 36 1 ;

36a 0 2 D 37 1 -

3 1 38 1 4 1 39 1 5 1 40 1 6 1 41 2 7 1 42 0 8 1 43 1 9 1 4 1 10 1 45 1 11 1 46 2 12 1 47 1 13 , 1 48 1 l 14 1 49 1 15 2 50 1 16 1 51 1 17 1 52 1

, 18 1 53 1 19 1 54 1 20 1 55 1 o

^

21 2 56 1 22 1 57 1 22A 0 58 1 23- 1 59 1 24 1 60 1 25 1 4N1 1 26 1 26A 0 27 1 27A 0 :

28 1 29 1 30 2 30A 0 31 1 32 1 33 1 34 1 35 1 ,

D = Deletion ,

Rev. 4

~ _ .

O' IIcGUIRE NUCLEAR STATION - UNITS 1 AIS 2 Page 1 SLSet4RY OF EMIR 000 ENTAL QUALIFICATI0ft 0F CLASS 1E EQUIPIENT Rev. I LOCATED OLTSIDE CONTAlf0ENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION EfRflR000ENT EQUIP 9ENT ID: Boric Acid Transfer Pump Mators MANUFACTURER: ChampumpAdestinghouse IIDDEL #: Champump Model.

(1) GUH"10K-12H-15 RECIRCULATION RADIATION RADIATION LEVEL 10 WHICH EWIR000ENT QUALIFIED (TID) (2) (TID)

These motors are not required to operate in the post-LOCA recirculation radiation environment l

QUALIFICATI0ff REPORT: N/A NETH00: N/A NEQP

, u ~

e s . :. ->

?' . ?~ . .gf 1: ' ,

p) . ,

e McGUIRE NUCLEAR STATION --UNITS 1 AND 2 Page 3

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT .

Rev. 1 LOCATED OUTSIDE CONTAINMENT AND. EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT-

?

~

EQUIPMENT ID: Centrifugal Charging Pump Motors MANUFACTURER: Westinghouse, Buffalo MODEL #: 72F44587-1573, 72F44587-

/

(1) and Spare ~,

2S73, 72F445F,7-3573, 72F44587-4573

/

., 81F32008-1582-11 RECIRCULATION RADIATION f,c -E ~

RADIATION LEVEL TO WHICH ENVIRONMENT, QUALIFIED (TID) (2) <

j; (TID)

~

^

" 8.8X104 RAD 2X108 RAD QUALIFICATION REPORT: WCAP 8754 Rev. 1 (MCH-1318.00-0026), WCAP 7829 (MCM-1318.00-0027)

METHOD: Test and Analysis EPSR

.=

)

McGUIRE' NUCLEAR STATION - UNITS 1 AND 2 . .Page 4

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS.1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO-THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Containment Spray Pump Motors MANUFACTURER: Westinghouse, Buffalo MODEL #: 73F56019-1573,'73F56019-(1) 2S73, 73F56019-3573, 73F56019-4573 RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 5.2X10SRAD 2X108 RAD i

j i

i i

i QUALIFICATION REPORT: WCAP 8754 Rev. 1 (MCM-1318.00-0026), WCAP 7829 (MCM-1318.00-0027) 4 METHOD: Test and Analysis i

EPSR

+-

s McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 5'

SUMMARY

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

, EQUIPMENT ID: Fuel Pool Cooling Pump Motors NANUFACTURER: Westinghouse, Buffalo MODEL #: 72F44649-1574, 72F44649-2 (1) 2S74, 72F44650-1576, 1

72F44650-2576'

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

(TID)'

1 i

SX103 RAD 2X10sRAD t

i i

QUALIFICATION REPORT: WCAP 8754 Rev. 1 (MCM-1318.00-0026), WCAP 7829 (MCM-1318.00-0027) j METHOD: Test and Analysis i

i

EPSR

~ - - -

McGUIRE NUCLEAR STATION'- UNITS 1 AND 2 Page 6

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT- -

Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Residual Heat Removal Pump MANUFACTURER: Westinghouse, Buffalo MODEL'#: 71F13494-1572, 71F13494-(1) Motors 2S72, 71F13495-1572, 71F13495-2572 RECIRCULATION RADIATION RADIATION . LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) .(TID) 4.6X105 RAD 2X108 RAD QUALIFICATION REPORT: WCAP 8754 Rev. 1 (MCM-1318.00-0026), WCAP 7829 (MCM-1318.00-0027) 1 METHOD: Test and Analysis

! EPSR

.A r McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 7

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT- Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED T10 THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: RHR and Containment Spray Rooms MANUFACTURER: Reliance MODEL #: S/N 1YF-883032 (1) Sump Pump Motors RECIRCULATION RADIATION RADIATION LEVEL TO WHICH.

ENVIRONMENT QUALIFIED

-(TID) (2) (TID) 9.0X104 RAD 2X108 RAD QUALIFICATION REPORT: Radiation Qualification Report / Class 1E Small Powerhouse Motors (MCC-1381.05-00-0128)

METHOD: Analysis -

EPSR

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page'8

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED T0 THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT-EQUIPMENT-ID: Safety Injection Pump Motors MANUFACTURER: Westinghouse, Buffalo MODEL #: 73F69618-1575, 73F69618-(1) and Spare 2S75, 73F69618-3S75, 73F69618-4S75 81F32009-1582-12 RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 2.8X10sRAD 2X108 RAD QUALIFICATION REPORT: WCAP 8754 Rev. 1 (MCM-1318.00-0026), WCAP 7829 (MCM-1318.00-0027)

METHOD: Test and Analysis

(

, EPSR i

I - _ - . _ _ - - - - _ _ - - _ _ _

, .g McGUIRE NUCLEAR STATION - UNITS'l AND 2 Page 9f

SUMMARY

OF ENVIRONMENTAL l QUALIFICATION OF CLASS 1E EQUIPMENT. ..

Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT-EQUIPMENT ID: -Annulus Ventilation System MANUFACTURER: Joy / Reliance .MODEL #: 2YF-273608 (1) Fan Motors RECIRCULATION RADIATION

' RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 4X108 RAD IX107 RAD QUALIFICATION REPORT: Radiation Qualification Report / Class 1E Small Powerhouse Motors (NCC-1381.05-00-0128)

METHOD: Analysis MDSS

4

.d

-McGUIRE NUCLEAR STATION - UNITS l'AND 2 .Pagei10

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. l' LOCATED'0UTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT' 1

). EQUIPMENT ID: Auxiliary Building' Filtered MANUFACTURER: Reliance MODEL #: 1YF-882811, 1YF-882812' j (1) Exhaust Fan Motors and Spares. 1YF-882900, 1YF-882901

' RECIRCULATION RADIATION RADIATION LEVEL'TO WHICH-i ENVIRONMENT QUALIFIED.

(TID) (2) (TID) l i

3.0X105 RAD 2X108 RAD I'

~

. QUALIFICATION REPORT: Radiation Qualification Report / Class IE Small Powerhouse Motors l (MCC-1381.05-00-0128) i METHOD: Analysis j EPSR.

b

1 McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 11

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1

, LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Diesel Generator Ventilation MANUFACTURER: Joy / Reliance- MODEL' #: 1YF-273608

'(1) Fan Motors

RECIRCULATION- RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED

, (TID) (2) (TID) 2X104 RAD 1X107 RAD I

QUALIFICATION REPORT: Radiation Qualification Report / Class 1E Small Powerhouse Motors (MCC-1381.05-00-0128)

METHOD: Analysis

MDSS

l

.McGUIRE NUCLEAP, STATION - UNITS 1 AND 2 'Page ll2'

SUMMARY

OF ENVIRONMENTAk QUALIFICATION OF. CLASS 1E EQUIPMENT. . .

Rev. 1 LOCATED OUTSIDE CONTAINMENT.AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT 1 EQUIPMENT ID: Fuel' Pool C'ooling Pump. Air. MANUFACTURER: Reliance. MODEL #: .3YF-882311, 1YF-882311 (1) Handling Unit Fan Motors & Spares RECIRCULATION RADIATION RADIATION LEVEL-T0 WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID)

SX103 RAD 1X108 RAD S/N 3YF-882311 2X10sRAD S/N 1YF-882311 QUALIFICATION REPORT: Radiation Qualification Report / Class IE Small Powerhouse Motors (MCC-1381.05-00-0128)

METHOD: Aaalysis I

EPSR f

McGUIRE NUCLEAR STATION - U:11TS 1 AND 2 . Page 13

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 i LOCATED OUTSIDE CONTAINHENT AND EXPOSED'TO THE POST-LOCA. RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: RHR Pump.and CS Pump Air MANUFACTURER: Reliance MODEL #: 2YF-882311, 1YF-882311 (1) Handling Unit Fan Motors & Spares RECIRCULATION RADIATION

.i.

RADIATION LEVEL TO WHICH

ENVIRONMENT QUALIFIED

(TID) (2) (TID)

R 5.2X105 RAD 2X10sRAD 1

i i

i l QUALIFICATION REPORT: Radiation Qualification Report / Class IE Small Powerhouse Motors (MCC-1381.05-00-0128) l METHOD: Analysis

{

I I

j EPSR 1

McGUIRE NUCLEAR. STATION - UNITS 1 AND 2 .Page 14 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS.IE' EQUIPMENT _

Rev.=1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT' EQUIPMENT ID: 600 Volt Load Centers MANUFACTURER: Gould MODEL #: K-Line (1) Worst case: 1ELXD & 2ELXD RECIRCULATION RADIATION

, RADIATION. LEVEL TO WHICH ,

ENVIRONMENT QUALIFIED t (TID) (2)' (TID) 1 1

6X104 RAD 1X105 RAD l

i i

QUALIFICATION REPORT: Gould Report (MCM-1312.03-165, OM-301-80).

t METHOD: Test and Analysis

1 f EPSA

r, r

McGUIRE NUCLEAR STATION - UNITS l'AND 2- Page 15l

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 2 LOCATED OUTSIDE CONTAINMENT-AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Motor Control Centers MANUFACTURER: Nelson Electric ~ MODEL #: Class 1035U (1) Worst case: IEMXB4 and 2EMXB4 .

RECIRCULATION- RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED t

(TID) (2)- (TID) 5 6X104 RAD 1X105 RAD i

j QUALIFICATION REPORT: MCM-1314.01-246 J

METHOD: Test and Analysis EPSA

.s q

McGUIRE NUCLEAR STATION - UNITS 1 AND 2- -Page 16 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev.'l-LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT:

EQUIPMENT ID: Diesel Batteries = MANUFACTURER: Nife . MODEL #: HIP-4 (1) Worst Case: 1EDG8 RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT '

QUALIFIED (TID) (2) (TID)'

5X103 RAD (Note 4)

QUALIFICATION REPORT: (Note 4)

METHOD: (Note 4) i EPSS I

0.

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 17

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Diesel Battery Chargers MANUFACTURER: Power Conversion MODEL #: 3S-130-100CE (1) Worst Case: 1EDGB Products RECIRCULATION RADIATION RADIATION LEVEL TO WHICH

, ENVIRONMENT QUALIFIED i (TID) (2) (TID)

SX103 RAD (Note 4) t l

j i

1

)

i QUALIFICATION REPORT: (Note 4) l l METHOD: (Note 4) j EPSS

i

, McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 18

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev.:1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Potential Transformers, in MANUFACTURER: Westinghouse MDDEL #: PTM 75-(1) RCP Switchgear _

j Worst Case: RCP-1D and RC.-2D RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID)-(2)- (TID) 4 4X104 RAD 4X104 RAD l

I i

}

i 1

l QUALIFICATION REPORT: Report MCM-1312.07-46 i METHOD: Test and Analysis 1

r

! EPSA

l

,,n; ~ ~ -

,;,, '* 1 McGUIRE NUCLEAR STATION - UNITS'1'AND 2 Page.19

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT .

'Rev. 1 LOCATED OUTSIDE' CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Valve Motor Operators . MANUFACTURER: Limitorque MODEL #: SMB Limitorque' Order (1) Order Numbers: 375826-A,'

375829-A, 375831-A, 375832-A, 375833-A,.

375834-A,'375835-A, 379664-B, 379857-A RECIRCULATION. RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID)

SX108 RAD 2X107 RAD (worst case)

QUALIFICATION REPORT: Limitorque Test Report B0058, Appendix D, dated 1/11/80 (MCM-1205.34-0002) i METHOD: Test I

.i l MEQP i

l __ _ _ _ _ _ _ - _ ___

e

- McGUIRE i;UCLEAR STATION - UNITS 1 AND 2 Page 20

SUMMARY

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

EQUIPMENT ID: Valve Motor Operators. MANUFACTURER: Limitorque MODEL #: Limitorque Order Numbers:

(1) 383584-A and 391179-A, B RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED ,

(TID) (2) (TID)

SX108 RAD 2X10sRAD i (worst case)

QUALIFICATION REPORT: Limi.orque Test Report B0058, Appendix B, dated 1/11/80 (MCM-1205.34-0002)

METHOD: Test i

i i MEQP 4

4 ..

4 McGUIRE NUCLEAR' STATION - UNITS 1 AND 2' .

Page 21 SUW4ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS'1E EQUIPMENT. Rev. 2 ,

LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE. POST-LOCA RECIRCUi.ATION RADIATION ENVIRONMENT EQUIPMENT 10: Valve Motor Operators MANUFACTURER: 'Rotork MODEL #: NA-2 2

(1)

RECIRCULATION PADIATION RADIATION LEVEL TO WHICH.

, ENVIRONMENT QUALIFIED

(TID): (2) (TID) i i SX108 RAD 3X107 RAD l (worst case)

I l

QUALIFICATION REPORT: Rotork Test Report N14/2 dated 5/70_(MCM-1205.34-0001), Rotork Test Report 3059 (MCM-1205.34-1) l METHOD: Test i

MEQP i

I

.s McGUIR.E NUCLEAR STATION - UNITS 1 AND 2 Page'22 ,

Sut#4ARY.0F ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. l' LOCATED OUTSIDE CONTAINMENT'AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: . Valve Motor Operators MANUFACTURER: Rotork' MODEL #: NA-1 (1) (S/N<4800)

RECIRCULATION RADIATION

~ RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) ' (TID) 5X10sRAD 2X10sRAD (worst case)

QUALIFICATION REPORT: Rotork Test Report TR-116, datad 10/73 (MCM-1205.34-0001)

METHOD: Test

MEQP

r

j McGUIRE NUCLEAR STATION - UNITS 1 AND 2 'Page 22A

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT < Rev. O LOCATED OUTSIDE CONTAINMENT'AND EXPOSED T0'THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Valve Motor Operators MANUFACTURER: Rotork' MODEL #: NA-1_ .

(1) (S/N>4800)

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

- 5X106RAD 2X10sRAD (worst case) e QUALIFICATION REPORT: Wyle Report 43979-1 Rev. A dated December 19, 1978 (MCH-1205.34-0010)

METHOD: Test MEQP I

.a .

.McGUIRE NUCLEAR STATION - UNITS 1 AND'2 Page 23

' Rev.<1 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS -1E EQUIPMENT .

LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID:' Valve Solenoid Operators MANUFACTURER: Valcor MODEL #: .V526, V573-(1)

RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 4

SX108 RAD 2X108 RAD (worst case)

)

l QUALIFICATION REPORT: Valccr Test Report QR-52600-5940-2, dated July 5, 1979 (MCM-1205.34-0012) i METHOD: Test l

i

.i

McGUIRE NUCLEAR STATION - UNITS l'AND 2 Page 24

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT _

Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Valve Solenoid Operators MANUFACTURER: Valcor MODEll: V70900-21-3 (1)

RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 1.1x108 RAD 2X108 RAD (worst case).

i l

QUALIFICATION REPORT: Valcor Test Report QR-70900-21-1 Rev. A (MCM-1210.04-0118); QR-52600-515, Rev. B (MCM-1210.04-0115);

MR70905-21-3-1 (MCM-1210-04-0119)

METHOD: Test Similarity MPIC

.s s

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 25 SUM 4ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT- Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT i EQUIPMENT ID: Valve Solenoid Operators MANUFACTURER: ASCO- MODEL #: NP8316E34E (1)'

RECIRCULATION- RADIATION

RADIATION. LEVEL TO WHICH

._'~

ENVIRONMENT QUALIFIED (TID) (2) (TID).

l 1.1x108 RAD 2X108 RAD (worst case) i a

QUALIFICATION REPORT: ASCO Test Report AQS21678/TR (MCM-1210.04-0117) l METHOD: Test.

i I

MPIC

McGUIRE NUCLEAR STATION - UNITS 1 AND~2 Page.216

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE' CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Valve Stem Mounted Limit Switch MANUFACTURER: NAMC0 MODEL #: EA-170-302 (1) i RECIRCULATION- RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED j .(TID) (2) .(TID) 1X108 RAD 2X108 RAD (worst case) i 6

.l i

i QUALIFICATION REPORT: NAMCO Report QTR-107 dated 3/11/81 (MCM-1205.34-0011)

I METHOD: Test l

9 i

l MEQP i

e McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 271

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E. EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND. EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Valve Stem Mounted Limit Switch MANUFACTURER: NAMCO- MODEL #: .EA-180, EA-740 (1). (Unit 1)

. RECIRCULATION. RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) i i IX108 RAD 2X10sRAD l '(worst case) 1

[ QUALIFICATION REPORT: NAMCO Test Report QTR-106 dated September 2, 1981 (MCM-1205.34-0009) and -

i NAMCO Test Report QTR-111, Rev. O dated 10/01/81 (MCM-1205.34-0008) i METHOD: Test 4

MEQP 1

McGUIRE NUCLEAR STATION - UNI!S 1 AND 2 Page 28

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Motor Operated Dampers MANUFACTURER: Rotork MODEL #: 7A (1)

RECIRCULATION PADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 3X107 RAD 3X107 RAD (worst case)

QUALIFICATION REPORT: Rotork Test Reports NI4/2 (MCM-1205.34-0001); Supplemental Information (MCM-1211.00-1563)

METHOD: By similarity to Rotork NA2 Operator .

i MDSS

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 29 SUMARY OF ENVIROMENTAL QUALIFICATION OF CLASS IE' EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAlletENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Three-Way Solenoid Valve MANUFACTURER: Powers MODEL #: 265-0002 (1)

RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 1.05X10 8RAD- 1.16X108 RAD QUALIFICATION REPORT: Test Specification MCS-1211.00-06, Supplement 10; Test Report A-490-82 (MCM-1211.00-1645); Report A-320-80-02 (MCM-1211.00-1524) s

-METHOD: Test _

6 MDSS

,r_!- % 5- 9:y

' ~. . . ~

. , .:g 5, . .%. . . , , '

, .s - a. -

s.

"'t -

j : ~~ ' , . ,

j ~~

j _} f: ~ ,,~ LQ , %;

h9 N

.- -- s .

.[ [~ a y _ :y U

C MN' s

{'

~ '

,r -2... .

y .o- , j';;

. .. McGUIRE NUCLEAR. STATION - UNITS 1 AND 2.s. O.' Page 30 Su MARY OF ENVIRONMENTAL QUALIFICATION OF: CLASS'1E EQUIPMENT .Rev. 2~

LOCATED OUTSIDE CONTAINMENT'AND EXPOSED.T0 THE POST-LOCA' RECIRCULATION RADIATION ENVIRONMENT.

EQUIPMENT-ID: Annulus Vent Filter Unit MANUFACTURER; Farr"j MODEL #: N/A' ..

(1) Control Panels "

.w. ,

r i . RECIRCULATION RADIATION RADIATION LEVEL TO WHICH

ENVIRONMENT ~

QUALIFIED (TID) (2) .(TID),. .

.o, y- . '

,I$

},S

~~

- . These panels have been relocated to'a mi1d environment ~ _

, fj

, ~. , -

4 QUALIFICATION REPORT: N/A

METHOD: N/A -

L

~

MDSS

.e

,3 ..-

~

4-McGUIRE NUCLEAR' STATION - UNITS 1 AND 2 'Page 30A

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT . Rev. 0 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE' POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT'ID: Annulus Ventilation Filter MANUFACTURER: Farr MODEL #: N/A *

', (1) Unit Preheater and Controls f

RECIRCULATION RADIATION RADIATION LEVEL TO WHICH

ENVIRONMENT QUALIFIED l (TID) (2) (TID) 4.06x107 RADS 4.5x107 RADS e ,

QUALIFICATION REPORT: Test Report MCM-1211.00-1685 i

i

, METHOD: Test and Analysis MDSS

McGUIRE NUCLEAR STATION - UNITS'1 AND 2 .

Page 31. #

- SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT .

Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE: POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: ABFU Control Panels MANUFACTURER: Allison MODEL #: N/A (1)

RECIRCULATION RADIATION

~ RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID)

These panels are non-safety-related, and their failure in the harsh radiation environment will not preclude accomplishment of a. safety-related function.

QUALIFICATION REPORT: N/A METHOD: N/A i

MDSS

O I .,

1

.McGUIRE NUCLEAR STATION - UNITSI l AND.2 Page 32L

SUMMARY

OF. ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT- 'Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED T0 THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Proportional Temperature . MANUFACTURER: Love Controls. MODEL #: 54 .834 .838- 8134 (1) Controller -8160- 8187- 8173 .8174-RECIRCULATION RADIATION l RADIATION LEVEL TO WHICH l ENVIRONMENT- QUALIFIED (TID) (2) (TID) 2.05X104 RAD 2.26X104 RAD l

8 -

l l

QUALIFICATION REPORT: Test Specification MCS-1211.00-05, Supplement 10; Test Report A-490-82 (MCM-1211.00-1645); Report A-320-80-02 (MCM-1211.00-1524)

I 4

METHOD: Test MDSS

+

-McGUIRE NUCLEAR STATION - UNITS 1 AND 2 . .Page'33

SUMMARY

.0F ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT: . Rev. l'

LOCATED OUTSIDE CONTAINMENT AND EXPOSED'TO THE POST-LUCA RECIRCULATION RADIATION ENVIRONMENT-EQUIPMENT ID: High Temperature Detection MANUFACTURER: United' Electric MODEL #: 800G-6CS' l (1) Thermostat-REClRCULATION RADIATION

RADIATION . LEVEL TO WHICH ENVIRONMENT . QUALIFIED

(TID) (2) (TID) 1.05X108 RAD 1.16X108 RAD e

i i.

1 l QUALIFICATION REPORT: Test Specification MCS-1211.00-0C, Supplement 10; 1 Test Report A-490-82 (MCM-1211.00-1645); Report l A-320-80-02 (MCM-1211.00-1524) i

, METHOD: Test

! MDSS .

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 34

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Resistance Temperature Detector MANUFACTURER: Weed MODEL #: 101-1.2N-A-3-C-6-A2-1:

(1)

RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) i 2.05X104 RAD 2.26X104 RAD t

I QUALIFICATION REPORT: Test Specification MCS-1211.00-06, Supplement 10; Test Report A-490-82 (MCM-1211.00-1645);

Report A-320-80-02 (MCM-1211.00-1524)

METHOD: Test MDSS 4

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 . Page 35

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED T0 THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT-EQUIPMENT ID: Differential Pressure Switch MANUFACTURER: Solon MODEL #: -7PSIDW-(1)

RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 1.65X10 GRAD 1.82X108 RAD QUALIFICATION REPORT: Test Specification MCS-1211.00-06, Supplement 10; Test Report A-490-82 (MCM-1211.00-1645);

Report A-320-80-02 (MCM-1211.00-1524)

METHOD: Test MOSS a

McGUIRE NUCLEAR STATION - UNITS-1 AND 2 Page 36:

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT :Rev. 1-

-LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Differential Pressure Switch MANUFACTURER: Solon MODEL #: 7PSIADW (1)

RECIRCULATION RADIATION

-RADIATION LEVEL TO WHICH-

-ENVIRONMENT QUALIFIED (TID) (2) (TID) 1.05x10 RAD 1.16X108 RAD QUALIFICATION REPORT: Test Specification MCS-1211.00-06, Supplement 10; Test Report A-490-82 (MCM-1211.00-1645);

Report A-320-80-02 (MCM-1211.00-1545)

METHOD: Test MDSS

.McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 36a SUM 4ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT .

Rev. O LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO.THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT

' EQUIPMENT ID: Pressure Transmitter - MANUFACTURER: Barton 'MODEL #: 7PSIADW

! (1) Annulus Pressure t RECIRCULATION -

RADIATION i RADIATION LEVEL TO WHICH s ENVIRONMENT QUALIFIED (TID)-(2) (TID) 4 i

{ 1.0X103 RAD 2X108 RAD

.l l

i QUALIFICATION REPORT: Wyle Report #43904-1, Vol.-I - 6 '. C, Vol. II - Rev. B (MCM-1210.04-0016) s METHOD: Test l MPIC i

4

7- .,

1 McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 37'

SUMMARY

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

, EQUIPMENT ID: Limit Switch MANUFACTURER: Micro Switch MODEL #: LSM4N (1)

RECIRCULATION RADIATION RADIATION LEVEL TO WHICH j ENVIRONMENT QUALIFIED (TID) (2) (TID) i This equipment will be removed from safety power before startup after the first refueIing.

This equipment presently serves an indication function only and is not used by the operator as a basis for any required action.

I t

QUALIFICATION REPORT: N/A METHOD: N/A MDSS

4 McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 38 Sul#4ARY OF ENVIRONMENTAL QUALIFICATION OF. CLASS 1E EQUIPMENT Rev. 1-LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Terminal Blocks MANUFACTURER: . Buchanan MODEL #: 0721 and P0721 (1)

RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 1.05X108 RAD 1.16X108 RAD QUALIFICATION REPORT: Test Specification MCS-1211.00-06, Supplement 10; Test Report A-490-82 (MCM-1211.00-1645);

Report A-320-80-02 (MCM-1211.00-1524)

METHOD: Test MOSS

. - . - - - ~ ,

~

4 - -

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 .

Page 39

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT Rev.:1

~ LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Control and Power Cable MANUFACTURER: Anaconda MODEL #: EP Insulation and (1) _ EP/Hypalon Insulation (Procurement Specs:

MCS-1354.01-2&4, & ,

MCS-1354.02-3,6&9)

RECIRCULATION '

RADIATION RADIATION LEVEL-T0 WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 1.1X10sRAD 2X10sRAD QUALIFICATION REPORT: Anaconda Test Reports F-C4350-2 (MCM-1354.00-0008) and F-C4350-3 (MCH-1354.00-0009)

METHOD: Test EPSS

c

~

Page'40

~

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 SUMARY OF ENVIRONMENTAL QUALIFICATION OF. CLASS 1E EQUIPMENT Rev. 11 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE' POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Control Cable MANUFACTURER: Brand Rex MODEL #: XLPE Insulation (Procuremer (1) Specs: MCS-1354.02-4,5,7,;

& 9, & MCS-1354.04-14)

RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT- . QUALIFIED (TID) (2) (TID) 1.1X10sRAD 2X10sRAD QUALIFICATION REPORT: Brand Rex Test Report FC4113 (MCM-1354.00-0007), FC5120-1 (MCM-1354.00-0023) and FC5120-3 (MCM-1354.00-0024)

METHOD: Test EPSS

9 McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page-41 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT Rev. 2 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Control, instrumentation, and Power MANUFACTURER: Okonite MODEL #: EP, EP/Hypalon and Hypalon (1) Cable Insulation (Procurement' Specs: MCS-1354.01-1&2, MCS-1354.02-4,6&9, &

MCS-1354.03-4)

RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 1.1X10sRAD 2X108 RAD QUALIFICATION REPORT: Okonite Test Reports N1, May 2, 1975 (MCM-1354.00-0010); FN-1, July 3, 1978 (MCM-1354.00-0013); G-3, June 28, 1979 (MCM-1354.00-0012); 110E November 12, 1970 (MCM-1354.00-0016); Duke Test Report TR032 (MCM-1354.00-0022);

G1, February 17, 1976 (MCM-1354.00-0045)

METHOD: Test EPSS

3 McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 43 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAI MENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Shielded Pair Armored MANUFACTURER: Brand Rex MDDEL #: PVC Insulation (1) Jacketed Instrumentation Cable RECIRCULATION RADIATI(,h RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 3X107 RAD .5X107 RAD QUALIFICATION REPORT: Duke Test Report TR032 (MCM-1354.00-0022)

METHOD: Test EPSS

L McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 44 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT- Rev.' 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT

) EQUIPMENT ID: Control Cable MANUFACTURER: Okonite MODEL #: Tefzel 280 Insulation (1) (Procurement Spec:

j MCS-1354.04-6) 4 RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 1.1X10sRAD 2X10sRAD t

QUALIFICATION REPORT: Okonite Test Report K-0-1, September 1979 (MCM-1354.00-0011) and K-8-1, April 4, 1981 (MCM-1354.00-0044) i HETH00: Test i

1 4

EPSS 1

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 45 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Instrumentation Cable MANUFACTURER: Eaton (Samuel Moore) MODEL #: EP/Hypalon Insulation (1) (Procurement Specs:

MCS-1354.03-1,2,3,&S

& MCS-1354.04-2&5)

RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 1.1X108 RAD 2X10sRAD f

i i

j QUALIFICATION REPORT: Samuel Moore Test Report F-C3683 (MCM-1354.00-0006)

METHOD: Test 4

EPSS

i e

McGUIRE NUCLEAR STATION - . UNITS 1 AND 2 .

Page 46 SumARY OF ENVIROMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 2 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Shielded Pair Armored MANUFACTURER: E'aton (Samuel Moore) ~ MDDEL #: ~PVC: Insulation 1 (1) Jacketed Instrumentation Cable RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 3X107 RAD SX107 RAD- .

QUALIFICATION REPORT: Duke QTF Report TR-032 (MCM-1354.00-0022)

METHOD: Test EPSS

4 k 2

McGUIRE NUCLEAR STATION'- UNITS 1 AND 2 Page 47 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT .Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Fuse MANUFACTURER: Bussmann MODEL #: FNA (1) (Note 6)

RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) , (TID) 1.6X108 RAD 1.6X108 RAD (worst case)

QUALIFICATION REPORT: Duke QTF Report TR-040 (MCM-1393.02-0006, ESSEM File III-A-4) ,

METHOD: Test ECSE

1f

/,$

~

McGUIRE NUCLEAR STATION -' UNITS 1 AND 2- Page 48.

SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT . .

.Rev. 1~

LOCATED OUTSIDE' CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRO MENT.

EQUIPMENT ID: ' Fuse Block : MANUFACTURER: Bussmann MODEL~#: -3792 (1)' (Note 6)'

RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID)-(2) (TID) 1.6X108 RAD. 1X10toRAD.

(worst case)

QUALIFICATION REPORT: Radiation Analysis (ESSEM File IV-A-3)

METHOD: Analysis ECSE

-McGUIRE NUCLEAR STATION -LUNITS 1 AND 2 . Page'49.

SUMARY OF ENVIRONNENTAL QUALIFICATION OF CLASS 1E EQUIPMENT .

Rev.'l LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE-POST-LOCA. RECIRCULATION RADIATION ENVIRONMENT' i

EQUIPNENT ID: Fuse Block MANUFACTURER: .Bussmann MODEL #: 14439 (1) (Note 6)

RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 1.1X103 RAD IX1010 RAD (worst case)

QUALIFICATION REPORT: Radiation Analysis (ESSEM File IV-A-3)

METHOD: Analysis ECSE

i McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 50

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev.'1:

LOCATED OUTSIDE CONTAINMENT AND-EXPOSED TO THE POST-LOCA' RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Fuse Block MANUFACTURER: Bussmann MODEL #: 4575 (Note 6)

RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 1X108 RAD 1X1010 RAD (worst case)

QUALIFICATION REPORT: Radiation Analysis (ESSEM File IV-A-3)

METHOD: Analysis ECSE

a McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 51.

SU M ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT .

Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Indicating Light MANUFACTURER: Cutler-Hammer MODEL #: E29 (1) (Note 6)

RECIRCULATION RADIATION

. RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID)

SX105 RAD 5X105 RAD (worst case)

QUALIFICATION REPORT: Duke QTF Report TR-040 (MCM-1393.02-0006, ESSEM File II-B-1)

METHOD: Test ECSE

i McGUIRE NUCLEAR STATION - UNITS 1 AND 2~ Page 52 SU M ARY OF ENVIRONMLNTAL QUALIFICATION OF CLASS 1E EQUIPMENT . Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIR0iMENT EQUIPMENT ID: Relay MANUFACTURER: Cutler-Hammer MODEL #: D23-(1) (Note 6)

/

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

IX108 RAD 1X108 RAD (worst case)

QUALIFICATION REFORT: Duke QTF Report TR-040 (MCM-1393.02-0006, ESSEM File VII-A-2.1)

METHOD: Test a

ECSE l

n. . ._

4 McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 53; SupMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT- Rev. 1-LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE. POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Relay MANUFACTURER: Cutler-Hanumer MODEL #: D26

-(1) (Note 6)

RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 3x105 RAD 1x10" RAD (worst case)

QUALIFICATION REPORT: Duke QTF Report TR-047 (MCM-1393.02-0007), ESSEM File VII-A-2.2)

METHOD: Test ECSE

6, McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 54 SU M ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT.

EQUIPMENT ID: Surge Suppressor MANUFACTURER: General Semiconductor MODEL #: Transzorb (1) (Note 6)

RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 1.6X108 RAD 2X107 RAD (worst case)

QUALIFICATION REPORT: General Semiconductor Specification; Radiation Analysis (ESSEM File III-C-1)

METHOD: Analysis ECSE

McCUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 55 SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Selector Switch MANUFACTURER: Cutler-Hasuner MODEL #: 10250T (1) (Note 6)

RECIRCULATION RADIATION RADIATION LEVEL TO WICH ENVIRONMENT QUALIFIED (TID) (2) (TID)

SX105 RAD SX105 RAD (worst case)

QUALIFICATION REPORT: Duke QTF Report TR-040 (MCM-1393.02-0006, ESSEM File VI-A-1,4)

METHOD: Test l

ECSE t

o l

McGUIRE NUCLEAR STATION - UNITS 1 AIS 2 Page 56 Ste9WtY OF EWIROMENTAL QUALIFICATION OF CLASS IE EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAlleENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION EWIR0000ENT EQUIPMENT ID: Terminal Block MANUFACTURER: States M00EL 3: 2 net and NT (1) (Note 6)

RECIRCULATION RADIATION RADIATIO *4 LEVEL TO idHICH E W IR0000ENT QUALIFIED (TID) (2) (TID) 1.8X10' RAD 3X107AAD (worst case)

# 4 em

'% g b% "" # A

+

_~

~

' ~ '

QUALIFICATION REPotiT: Radiation An lysis (ESSEM File IV-B-4 & IV-B-5) 3

, e s e %,

METHOD: Analysis ?

g +

p ,"

+\'%~ p

( '"% -% O g m' -

~

-- s ECSE

^

, , - -m ,. . . .-

~ * * .

w

_ _ 2_ , _ _ _ __.

? - _ _

. J:m r

+

,0;

~

, ^.,s. . ,

m . y -

a a McGUIRE NUCLEAR-STATION.- UNITS 1 AND 2 Page 57' SUMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT ' Rev. 1 LOCATED OUTSIDE CONTAINMENT _AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT ~

EQUIPMENT.ID: Switch and Indicating Light MANUFACTURER: Cutler-Hammer MODEL #: E30 (1)- (Note 6) 4

RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT- QUALIFIED *

(TID) (2) (TID)

[ _

?, ,

1.8X105 RAD .- 1.9X10SRAD- -

(wor'st case) ~ ' '; ,

QUALIFICATION REPORT: Duke QTF Report TR-040 (MCM-1393.02-0006, ESSEM File VI-C-1)

METHOD: Test r

a h

ECSE

McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 58

SUMMARY

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

EQUIPMENT ID: Fuse Block MANUFACTURER: Bussmann MODEL #: 2808 (1) (Note 6)

RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 1.1X103 RAD 7X108 RAD (worst case)

QUALIFICATION REPORT: Radiation Analysis (ESSEM File IV-A-11)

METHOD: Analysis ECSE i

McGUIRE NUCLEAR STATION - UNITS 1.AND 2 Page 59

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED OUTSIDE CONTAINMENT'AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Terminal. Block MANUFACTURER; ~Stanwick_ MODEL #: SLS (1) (Note 6)

RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 2X104 RAD 3X107 RAD (worst case)

QUALIFICATION REPORT: Duke QTF Report TR-047 (MCM-1393.02-0007) (ESSEM File IV-B-1.1)

METHOD: Test ECSE

l t.

'i McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 60

SUMMARY

OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT - Rev. 1 LOCATED OUTSIDE CONTAINMENT AND EXPOSED TO THE POST-LOCA RECIRCULATION RADIATION ENVIRONMENT EQUIPMENT ID: Fuse HANUFACTURER: Littelfuse MODEL #: Slo-Blo (1) (Note'6)

RECIRCULATION RADIATION RADIATION LEVEL TO WHICH ENVIRONMENT QUALIFIED (TID) (2) (TID) 3X10sRAD 3x107 RAD (worst case)

QUALIFICATION REPORT: Duke QTF Report TR-047 (MCM-1393.02-0007, ESSEM File III-A-7)

METHOD: Test

ECSE i

t: -

i ATTACHMENT 5 DUKE POWER COMPANY ON THE CATEGORY II GUIDELINES OF NUREG 0588 h- Rev. Page Rev. M Rev.

1 0 2 0 3 0 4 0 l 5 1 6- 0 7 0 8- 1 9 1 10 2 11 1-12 3 13 1 14 0 15 1

- 16 1

- 17 0 -

18 1 19 1 20 1 21 2

22. 0-

. DEL 40113W 01/11/84 Rev. 3

'T +4 y y a--- -g --%, e m. y,.- -opy -o y .,ogy -g ,-w,-g 9- ,5-- .p., y .,we. .g e g g ,p-g . gm y - r,. - +

. MCGUIRE NUCLEAR STATION NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION l

1 1.0 ESTABLISHMENT OF THE QUALIFICATION PARAMETERS FOR DESIGN BASIS EVENTS l 1.1 . Temperature and Pressure Conditions Inside Containment -

Loss-of-Coolant 1.1.1 The time-dependent temperature The containment structural design and pressure, established for the has been based on the results on design of the containment struc- an analysis performed by Westing-ture and found acceptable by the house employing the methodology

' staff, may be used for environ- described below. The results of mental qualification of equip- this analysis are reported in Sec-ment. tion 6.2 of the FSAR.

1.1.2 Acceptable methods for calculat- Westinghouse employs the methodology ing and establishing the contain- described in WCAP-8312A for calculat-ment pressure End temperature ing the LOCA mass and energy release.

should be qualified are summarized Appendix A to NUREG-0588 indicates below. Acceptable methods for cal- that this methodology is acceptable culating mass and energy release to the Staff.

rates are summarized in Appendix A.

Pressurized Water Reactors (PWRs)

Ice Condenser Containment - Calcu- Westinghouse conforms to the Staff late LOCA containment environment position for Ice-Condenser Plants using LOTIC or equivalent industry by employing LOTIC to calculate the codes. Additional guidance is pro- containment transient following LOCA.

vided in SRP Section 6.2.1.1.B, NUREG-75/087.

1.1. 3 In lieu of using the plant-specific Plant-specific profiles are the containment temperature and pressure basis for McGuire equipment quali-design profiles for BWR and ice fication. testing.

condenser types of plants, the gen-eric envelope shown in Appendix C may be used for qualification test-ing.

EL40113W - 01/11/84 Rev. O L

NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 1.1.4 The test profiles included in Plant specific profiles are the basis Appendix A to IEEE Std. 323-1974 for McGuire equipment qualification should not be considered an ac- testing. It should be noted that the

.ceptable alternative in lieu of IEEE 323-1974, Appendix A temperature using plant specific containment and pressure profiles envelop the temperature and pressure design worst-case McGuire containment acci-profiles unless plant-specific dent temperature and pressure condi-analysis is provided to verify tions and have been used by some manu-the adequacy of those profiles. facturers for generic qualifications.

1.2 Temperature and Pressure Conditions Inside Containment -

Main Steam Line Break (MSLB) 1.2.1 Where qualification has not The environmental qualification been completed, the environmen- testing for equipment located in-tal parameters used for equip- side containment has been completed.

ment qualification should be calculated using a plant-speci-fic model based on the staff-approved assumptions discussed in Item 1 of Appendix B.

1.2.2- Models that are acceptable for Westinghouse employs the methodology calculating containment parameters described in WCAP 8822 for calculat-are listed in Section 1.1.2. ing the mass and energy release fol-lowing a Main Steam Line Break (MSLB).

At the specific request of Duke, Westinghouse has completed the mass and energy release calculations assum-

[ ing no entrainment. Westinghouse conforms to the Staff position for Ice-Condenser Plants by employing LOTIC to calculate the containment transient following MSLB.

1.2.3 In lieu of using the plant- Plant specific profiles are the specific containment temperature basis for McGuire equ*pment quali-and pressure design profiles for ficaticn testing.

BWR and ice condenser plante, the generic envelope shown in Appendix C may be used.

EL40113W - 01/11/84 Rev. O

NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 1.2.'4 The test profiles included in Plant specific profiles are the basis Appendix A to IEEE Std. 323-1974 for McGuire equipment qualification should not be considered an testing. It should be noted that the acceptable alternative in lieu of IEEE 323-1974, Appendix A temperature using plant-specific containment and pressure profiles envelope the temperature and pressure design worst-case McGuire containment accident profiles unless plant-specific temperature and pressure conditions analysis is provided to verify the and have been used by some manufacturers adequacy of those profiles. for generic qualificaticns.

1.2.5 Where qualification has been The environmental qualification tests completed but only LOCA condi- for equipment installed inside the tions were considered, then it containment at McGuire that is required must be demonstrated that the to function during and following a MSLB LOCA qualification conditions envelope the maximum calculated MSLB exceed or are equivalent to the conditions.

maximum calculated MSLB conditions.

1.3 Effects of Chemical Spray 1.3.1 The effects of caustic spray Chemical spray is included in quali-should be addressed for the fication tests for equipment located equipment qualification. The inside the containment provided the concentration of caustics used equipment is required to operate in for qualification should be the spray environment.

equivalent to or more severe than those used in the plant i containment spray system.

1.3.2 If the chemical composition of In the McGuire containment spray

the caustic spray can be affected system, no single failure can occur i

by equipment malfunctions, the that wil.1 result in a more severe most severe caustic spray environ- spray solution composition than the ment that results from a single anticipated composition.

failure in the spray system should be assumed. See SRP Section 6.5.2 (NUREG-75/087), Paragraph II, Item (e) for caustic spray solution guidelines.

EL40113W - 01/11/84 Rev. 0

NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 1.4 Radiation Conditions Inside and Outside Containment The radiation environment for The calculated radiation environ-qualification of equipment should ment is based on the 40 year normal be based on the normally expected operation dose plus the appropriate radiation environment over the DBA dose.

equipment qualified life, plus that associated with the most severe design basis accident (DBA) dur-ing or following which that equip-ment must remain functional. It should be assumed that the DBA-related environmental conditions occur at the end of the equipment qualified life.

The sample calculations in Appendix D and the following positions provide an acceptable approach for establishing radiation limits-for qualification. Additional radiation margins identified in Section 6.3.1.5 of IEEE Std. 323-1974 for qualification type

-testing are not required if these methods are used.

1.4.1 The source term to be used in The radiatien environments through-determining the radiation environ- out the station following a DBA ment associated with the design LOCA are determined assuming instan-basis LOCA should be taken as an taneous release from the fuel to the instantaneous release from the fuel containment of 100% of the noble gas to the atmosphere of 100 percent inventory, 50% of the core iodine in-

.of the noble gases, 50 percent of ventory, and 1% of the remaining core the iodines, and 1 percent of the fission product inventory. This source i remaining fission products. For term is used to derive radiation levels all other non-LOCA design basis for all equipment requiring radiation accident conditions, a source term qualification. The release fractions involving an instantaneous release are consistent with TID-14844 and from the fuel to the atmosphere of NUREG 0578, Item 2.1.6b.

10 percent of the noble gases (ex-cept Kr-85 for which a release of-l 30 percent should be assumed) and l 10 percent of the iodines is acceptable.

EL40113W - 01/11/84 Rev. 0 I

NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 1.4.2 The calculation of the radiation All radioactivity released initially environment associated with de- remains within the containment. For sign basis accidents should take conservatism airborne radioactivity is into account the time-dependent assumed to be homogeneously distributed transport of released fission throughout the containment at the products within various regions initiation of the accident. Recircula-of containment and auxiliary tion of water from the containment sump structures. is assumed to begin at 10 minutes into the accident. Prior to initiation of recirculation, normal radiation environments are assumed to exist throughout the station outside con-tainment. The time-dependent transport mechanisms considered are consistent with NUREG 0578, Item 2.1.6b.

1.4.3 The initial distribution of activ- See the response to 1.4.2 above.

ity within the containment should be based on a mechanistically ra-tional assumption. Hence, for com-partmented containments, such as in a BWR, a large portion of the source should be assumed to be in-itially contained in the drywell.

The assumption of uniform distri-bution of_ activity throughout the containment et time zero is not appropriate.

1.4.4 Effects of ESF Systems, such as To increase the conservatism of the l containment sprays and contain- calculated radiation values, no credit

! ment ventilation and filtration is taken for removal processes such as l

systems, which act to remove air- containment spray, filters, or natural borne activity and redistribute deposition. The only removal mechanism activity within containment, should considered is radioactive decay.

be calculated using the same as-sumptions used in the calculation of offsite dose. See SRP Section

~

15.6.5 (NUREG-75/087) and the re-lated sections referenced in the Appendices to that section.

t

-EL40113W - 01/11/84 Rev. 1

NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 1.4.5 ' Natural deposition (i.e., plate- The assumption of an instantaneous out) of airborne activity should plate-out of 50% of the iodine released be determined using a mechanistic from the core is not used. As stated model and best estimates for the above, natural deposition is not used model parameters. The assumption in the development of post-LOCA ra-of 50 percent instantaneous plate- diation levels.

out of the iodine released from the core should not be made. Re-moval of iodine from surfaces by steam condensate flow or washoff by the containment spray may be assumed if such effects can be justified and quantified by a-nalysis or experiment.

1.4.6 For unshielded equipment located The gamma dose in containment is that in the containment, the gamma dose dose calculated at the centerpoint of and dose rate'should be equal to the containment. Shielding effects are the dose and dose rate at the considered for equipment located out-centerpoint of the containment side the crane wall and in the accumu-plus the contribution from loca- lator rooms.

-tion dependent sources such as the sump water and plate-out, un-less it can be shown by analyses that location and shielding of the

_ equipment reduces the dose and dose rate.

1.4.7 For unshielded equipment, the beta Beta dose calculations are consistent doses at the surface of the equip- with the gamma dose calculations as ment should be the sum of the air- discussed above. Also see the response borne and plate-out sources. The to 1.4.8 below.

airborne beta dose should be taken as the beta dose calculated for a point at the containment center.

.1.4.8 Shielded components need be All Class 1E equipment located in-qualified only to the gamma radi- side containment that is required to ation levels required, provided mitigate a LOCA, MSLB, or HELB in-an analysis or test shows that side the containment has sufficient the sensitive portions of the shielding to prevent the exposure of EL40113W - 01/11/84 Rev. 0

NUREG 0588 CATEGORY.II DUKE POWER COMPANY GUIDELINES POSITION 1.4.8 (Continued) (Continued) component or equipment are not ex- any organic materials associated posed to beta radiation or that with this equipment to a beta ra-the effects of beta radiation diation environment.

heating and ionization have no

~ deleterious effects on component performance.

1.4.9 Cables arranged in cable trays See the response to 1.4.8 above.

in the containment should be as- Additionally, armored cables are used sumed to be exposed to half the in safety-related applications inside beta. radiation dose calculated containment at McGuire; therefore, for a point at the center of the beta radiation effects on cable insula-containment plus the gamma ray tion is considered negligible.

dose calculated in accordance with Section 1.4(6). This reduction in beta dose is allowed because of the localized shielding by other cables plus the cable tray itself.

.1.4.10 Paints and coatings should be See the response to 1.4.6 and 1.4.7 assumed to be exposed to both beta above.

and gamma rays in assessing their resistance to radiation. Plate-out activity should be assumed to remain on the equipment surface unless the effects of the removal mechanisms, such as spray wash-off or steam condensate flow, can be justified and quantified by analysis or experiment.

1.4.11 Components of the emergency Radiation levels outside containment core cooling system (ECCS) lo- following a design basis LOCA are cated outside containment (e.g., based on the release fractions dis-pumps, valves, seals, and elec- cussed in 1.4.1 above. This released trical equipment) should be quali- activity is assumed to be retained fied to withstand the radiation in and diluted by water from safety El40113W - 01/11/84 Rev. 0

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

.NUREG 0588 CATEGORY II DUKE POWER COMPANY U : GUIDELINES POSITION

. v;

[1.4.11 ^(Continued) -(Continued) equivalent to that penetrating injection and. ice bed melt.~ Where the containment, plus the exposure appropriate, radiation penetrating from the sump fluid using assump- the containment is included. This tions consistent with the require- analysis is consistent with that re-ments stated in. Appendix K to 10 quired by NUREG 0578, Item 2.1.6b.

CFR Part 50.

~

$1.4.12 Equipment that may be exposed to Class 1E equipment that is exposed radiation doses below 104 rads to a radiation environment is evalu-

_ should not be considered to be ated for proper radiation qualifica-exempt from radiation qualifi- tion.

cation, unless analysis supported by test data is provided to verify 2

that these levels will not degrade the operability of the equipment

~

below acceptable values.

' 1.4.13 The Staff will. accept a given The calculated radiation environ-component to be qualified pro-

~

ments for McGuire are comparable

- vided it can be shown that the to those values presented in

- component has been qualified to Appendix D.

integrated-beta and gamma doses

which are. equal to or higher than

-those. levels resulting from an analysis-similar in nature'and scope to that included in Appendix D

(which uses the source term given in Item (1) above), and that the-

+

component' incorporates appropriate

. factors pertinent to the plant design and operating characteristics, as given in.these general. guidelines.

1.4.14 When a conservative analysis has See the response to 1.4.13 above.

~

u not.been provided by the applicant l -for Staff review, the Staff will

', fuse the radiation environment guide-lines. contained in Appendix D, suit-i ably corrected for the differences in reactor-power level, type, contain-

, ment _ size, and.other appropriate D ~ factors.

i-L l; EL40113W - 01/11/84 Rev. 1 L .

NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION

1. 5 Environmental Conditions For Out-Side Containment 1.5.1 Equipment located outside con- Equipment located outside the con-tainment that could be subjected to tainment that could be subjected to high-energy pipe breaks should be a postulated pipe break environment qualified to the conditions result- and that is required to either miti-ing from the accident for the dur- gate the break or bring the unit to ation required. The techniques a safe shutdown condition is qualified to calculate the environmental for the pipe break environment.

parameters described in Sections 1.1 through 1.4 (Category II) above The methods employed to evaluate pipe should be applied, breaks and to determine the 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.

1.5.2 Equipment located in general Equipm2nt located in general plant

. plant areas outside containment areas outside containment and not where equipment is not subjected exposed to a DBA environment is de-to a design basis accident envi- signed and/or qualified for the ronment should be qualified to environmental conditions postulated to the normal and abnormal range of occur at the equipment location as environmental conditions postu- derived from the Plant environmental lated to occur at the equipment design basis.

location.

1.5.3 Same as Category I; or, there For general plant areas outside con-may be designs where a loss of the tainment where the area temperature environmental support system may could be postulated to exceed the expose some equipment to environ- design temperature of the equipment ments that exceed the qualified in that area, a temperature monitoring limits. For these designs, appro- system is provided.

priate monitoring devices should be provided to alert the operator that abnormal conditions exist and to permit an assessment of the con-ditions that occurred in order to determine if corrective action, such as replacing any affected equipment, is warranted.

EL40113W - 01/11/84 Rev. 1

.< NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION e

' 2. 0 QUA'IFICATION METHODS 2.1 Selection of Methods

, 2.1.1 Qualification methods should a. For equipment required to perform conform to the requirements de- a safety function in a postulated fined in IEEE Std. 323-1971. LOCA,-MSLB, HELB, or post-LOCA recirculation radiation environ-ment, the environmental qualifica-tion methods meet the intent of IEEE 323-1971 requirements,

b. For the equipment not required to operate in a harsh accident envir-onment, environmental qualfification per IEEE 323-1971 was not required.

Rather, the equipment was designed and analyzed to assure that it maintains its required performance capability for the environmental conditions postulated to occur at the equipment location as derived from the environmental design basis. In general, factory performance / functional testing at ambient conditions i is completed on equipment prior to shipping and, for some items of equipment, a production unit may be tested at the specified maximum ambient temperature.

These production tests, together

! with the design _ specification l for the equipment, which specifies

! the environmental design parameters

, and engineering analysis, provides l sufficient assurance of equipment capability in accordance with

[-~ the Staff position under Item 2.1.4.

t t

2.1.2 The choice of the methods selected For equipment located inside

.is largely a matter of technical containment that is required to

( judgement and availability of in- perform a safety function in a formation that supports the con- postulated LOCA, MSLB, or HELB clusions reached. Experience has environment, environmental qualifi-

[. shown that~ qualification of equip- cation is in general by testing.

E ment subjected to an accident envi-For equipment located outside containment l- EL40113W - 01/11/84 Rev. 2

..- . . . , 4 _

NUREG 0588 CATEGORY II DilKE POWER COMPANY GUIDELINES POSITION 2.1.2 (Continued) (Continued) ronment without test data is not that is required to perform a safety adequate to demonstrate functional function in a postulated HELB or post-operability. In general, the staff LOCA recirculation radiation environ-will not accept analysis in lieu of ment, qualification is in general by test data unless (a) testing of the testing, analysis, manufacturer's spe-component is impractical due to- cific design, and/or combinations of size limitations, and (b) partial these methods.

type test data is provided to sup-port the analytical assumptions and The qualification method is provided conclusions reached. in the equipment tables.

2.1.3 The environmental qualification of equipment exposed to DBA environ-ments should conform to the follow-ing positicns:

The basis should be provided for The required duration of operability the time interval required for is based on assumptions in the FSAR operability of this equip.nent. accident anlaysis, system requirements, and/or the time the environment is expected to remain outside its normal range following a DBA.

The required and demonstrated duration of the safety function of equipment subject to a LOCA, MSLB, HELB, or post-LOCA recirculation radiation environ-ment is provided in the equipment tables.

The operability and failure cri- The primary purpose of equipment quali-teria should be specified and the fication is to reduce the potential safety margins defined. for common-mode failures due to pos-tulated environmental conditions. Equip--

ment will therefore be considered to have failed the test and/or analysis if the functional requirements identified in the attached tables cannot be met, unless an investigation can establish that the failure mechanism is not of common-mode origin or that plant specific analyses can demonstrate that the reduced capabil-

ity is acceptable.

In certain cases, failure criteria, per

, se, was not specified prior to qualifi-cation testing; however, the failure EL40113W - 01/11/84 Rev. 1

NUREG 0588 CATEGORY II DUKE POWER COMPANY

- GUIDELINES POSITION

. 1 2.1.3- (Continued) (Continued) of the equipment would have been an

. obvious failure (i.e., equipment would not function).

Margin is discussed in Section 3.0.

2.1.3a" Equipment that must function in Equipment that must perform a safety order to mitigate any accident function in a LOCA, MSLB, HELB, or should be qualified by test to post-LOCA recirculation radiation en-demonstrate its operability for vironment, is qualified by test and/or the time required in the environ- analysis. The acceptance criteria for mental conditions resulting from the test and/or analysis is that the that accident.

safety-related function must be demon-strated for the specified duration of operability in the postulated accident environment.

- 2.1.3b Any equipment (safety-related In general, the failure of safety-orenon-safety-related) that need related equipment that is not re-not function in order to mitigate quired to perform a safety function in any accident, but that must not a postulated harsh accident environment fail in a manner detrimental to is not detrimental to plant safety.

plant safety should be qualified

- by test to demonstrate its capa- The effects and consequences of adverse.

bility to withstand any accident environments on non-safety-related

- environment =for the time during equipment is discussed in a which it must not fail. February 23, 1983 Duke Power Company letter from Tucker to Denton.

F 2.1.3c Equipment that need not function Where an-item of safety-related equip-in order to mitigate any accident ment is located in.an area such that and whose' failure in any mode in it may be exposed to a LOCA, MSLB, HELB, any accident = environment is not or post-LOCA recirculation radiation en--

detrimental to plant safety need vironment but is not required to ;:erform' '

only be qualified for its non- any safety-function as a result of the

- accident service environment. breaks, the failure of such equipment, f- . due to the adverse environment, has been r Although actual-type testing is determined not to prejudice the safety l: preferred, other methods when functions of other equipment claimed justified may be found acceptable. in the accident analysis.

.The bases should be provided for concluding that such equipment is not required to function in order

. to mitigate any accident, and that .

its failure in any mode in any

!. accident environment is not detri-mental to plant safety.

l i

~

! EL40113W - 01/11/84 Rev. 3 l

" 4 -t =e ,- -5, . - *- vuwe n a w. . , , r w , , - - - - - + .e-gyw .r,--...e.<m.e.---w- -+v+e s .- .en mer ..m- - * =-w - =-,w-awae-.s-+m++w--r---- e=-----=w.=- = =

~-

.f '

C NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 2.1.4 For environmental' qualification of As stated in the response to Item

. equipment subject to events other .

2.1.lb, the design specification re-than a DBA, which result in abnor- quirements for equipment not required

. mal environmental conditions, ac-to function in a harsh environment

tual type. testing is preferred. together with factory performance /

-However, analysis or operating functional tests and engineering history, or any applicable com- analyses (including some cases where bination thereof, coupled with the testing is performed at maximum partial type test data may be. ambient conditions) provide the re-found acceptable, subject to the quisite assurance for equipment ca-applicability and detail of in- pability.

foraiation provided.

. 2.2 : Qualification by Test 2.2.1 The failure criteria should be The response to Item 2.1.3 is appli-established prior to testing, cable for equipment required to operate in a LOCA,~MSLB, HELB, or post-LOCA

'2.2.2 Test results should demonstrate reicruciation radiation environment.

that the equipment can perform its required function for all service As stated in Item 2.1.la environmental

!' conditions postulated (with margin) qualification demonstrates the capa-during its installed life, bility of equipment to perform safety-related functions when subject to the consequential adverse environment of p LOCA, MSLB,-HELB, or post-LOCA recir-culation radiation. For equipment not required to operate in a harsh environ-ment, the-response to Item 2.1.lb applies.

e The requirement to demonstrate this i capability during the. installed life

l. implies an addressment of aging. This p subject is discussed under-Item 4. The subject of margin is discussed under Item 3.

2.2.3 The items described in Section 5.2 The Duke Power Company position with of IEEE Std. 323-1971 supplemented respect to Section 5 of IEEE 323-1971 is

.by Items (4) through (12) below provided in the response to Item 2.3.3.

. constitute acceptable guidelines for establishing test procedures.

[:

tc i.

I

~

IEL40113W-01/11/84 Rev. 1 i.

~

w

NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 2.2.4 When establishing the simulated In general, a single profile, envelop-environmental profile for quali- ing both MSLB and LOCA, is used for fying equipment located inside qualification of equipment located containment, it is preferred that inside containment which is required a single profile be used that envel- to perform a safety function to mitigate ops the environmental conditions a LOCA or MSLB. The exceptions to the resulting from any design basis use of a single qualification envelope event during any mode of plant for LOCA and MSLB are, in general, when:

operation (e.g., a profile that envelops the conditions produced (a) A component is only required by the main steamline break and to mitigate against either the loss-of-coolant accidents). LOCA or MSLB. In such a case, qualification has been completed to conditions enveloping the possible consequences inside containment from the single event and, additionally, it is verified that failure of the component in any other more limiting environment will not prejudice any safety-related function.

(b) The resulting test conditions would unjustifiably exceed acceptable conservatism.

2.2.5 Equipment should be located above In general, salety-related equipment flood level or protected against is located above the maximum post-submergence by locating the equip- LOCA water level. The exceptions to ment in qualified watertight en- this design philosophy are certain closures. Where equipment is motor operated valves and associated located in watertight enclosures, cables. The submerged valves are dis-qualification by test or analysis cussed in FSAR Section 15.4.1.3.

should be used to demonstrate the adequacy of such protection. Where equipment could be submerged, it should be identified and demon-strated to be qualified by test for the duration required.

EL40113W - 01/11/84 Rev. O

I~

NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 2.2.6 The temperature to which equipment In performing qualification tests for is. qualified, when exposed to the equipment exposed to a LOCA, MSLB, or simulated accident environment, HELB environment, the external environ-should bc defined by thermocouple ment temperature is measured as close to readings on'or as close as prac- the equipment surface as practicable.

tical to the surface of the compo-nent being qualified.

If there were no thermocouples located near the equipment during the tests, heat transfer analysis should be used to determine the temperature at the component.

(Acceptable heat transfer analysis methods are provided in Appendix B.)

2.2.7 Performance characteristics of Where the safety-related function of equipment should be verified the equipment requires operation in before, after, and periodically the LOCA, MSLB, HELB, or post-LOCA during testing throughout its recirculation radiation environment, range of required operability. the equipment performance before, dur-ing (w'ere n practical) and after expo-sure to the simulated event is veri-fied.

2.2.8 Caustic spray should be incor- The response to Item 1.3.1 is appli-porated during simulated event cable for equipment located inside con-testing at the maximum pressure tainment and qualified by test to oper-and at the temperature conditions ate in the LOCA or MSLB environment.

that would occur when the onsite spray systems actuate.

2.2.9 The operability status of equipment The response to Item 2.2.7 is appli-should be monitored continuously cable.

during testing. For long-term testing, however, monitoring at discrete intervals should be justi-fied if used.

2.2.10 Expected extremes in power supply Class 1E equipment is supplied by voltage range and frequency should guaranteed stabilized power supplies.

be applied during simulated event As a consequence, the range of the environmental testing. electrical parameters is considered to be within equipment capability.

EL40113W - 01/11/84 Rev. 1

. NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 2.2.11 Dust environments should be Duke has implemented housekeeping pro-addressed when establishing quali- cedures to preclude adverse dust con-fication service conditions. ditions at McGuire. Therefore, dust environments are not required as a qualification parameter.

2.2.12 Cobalt-60 is an acceptable gamma In general, Cobalt-60 sources are radiation source for environmental used to simulate the effects of gamma qualification. radiation for equipment qualified by test to operate in a LOCA/MSLB or post-LOCA recirculation radiation environment.

2.3 Test Sequence 2.3.1 Justification of the adequacy of In general, when testing is used to the test sequence selected should qualify equipment required to perform be provided. a safety function in a LOCA, MSLB, or HELB environment, the following test p sequence is employed:

1. The equipment is subjected -

to a calibration and/or veri-fication test at ambient con-ditions. This test included verification of safety-related functions.

2. No specific abnormal tests are required since the accident

, environment envelops the ab-normal condition with margin.

! 3. The equipment is irra-diated, using a Cobalt-60 source, to the estimated worst case gamma dose ob-tained from in-service oper-ation and required ac-cident and post-accident performance.

4. The same equipment is test-ed to verify equipment capa-bility during a simulated seismic event.

EL40113W --01/11/84 Rev. 1

'NUREG-0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 2.3.1 _(Continued) (Continued)

5. The same equipment is test-ed under applicable simulated accident and post-accident conditions.

Completion of the above test sequence gives assurance that the equipment can perform safety-related functions under normal, abnormal and design basis event conditions. The design basis event testing applies extremes of radiation, vibration (seismic), temperature, humid-ity and chemical spray in a conservntive sequence and verifies that the equipment being qualified is not marginal with respect to these parameters. The subject of margin and aging are dis-cussed under Items 3 and 4, respectively.

2.3.2 The test should simulate as For equipment that is qualified by closely as practicable the pos- testing, the test environment simulates tulated environment. as closely as practicable the postulated environment.

2.3.3 The test procedures should In general, the qualification testing conform to the guidelines de- of safety-related equipment at McGuire scribed in Section 5 of IEEE Std. conforms to the guidelines of IEEE 323-323-1971. 1971. The Duke position with respect to the documentation requirements of IEEE 323-1971 is provided in the response to Item 5.2.

2.3.4 The Staff considers that, for For equipment which is qualified by vital electrical equipment such testing and which is required to per-as penetrations, connectors, form a safety function in a LOCA, MSLB, cables, valves and motors, and or HELB environment, the test sequence transmitters located inside con- identified in the response to Item 2.3.3 tainaent or ex70 sed to hostile is generally employed and as a con-steam environments outside con- sequence does not, in general, employ tainment; separate effects test- effects testing, if used, is justified, ing for the most part is not an acceptable qualification method.

The testing of such equipment should be conducted in a manner i

that subjects the same piece of equipment to radiation and the hostile steam environment sequentially.

EL40113W - 01/11/84 Rev. O

NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 2.4 Other Qualification Methods Qualification by analysis or Duke does not necessarily rely on operating experience implemented, operating experience to establish as described in IEEE Std. 323-1971 the qualification of safety-related and other ancillary standards, may equipment, rather, operating experience be found acceptable. The adequacy may be included in support of quali-of these methods will be evaluated fication by test and/or analysis. The on the basis of the quality and equipment tables identify the qualifi-detail of the information submit- cation methodology employed for each ted in support of the assumptions item of safety-related equipment.

made and the specific function and location of the equipment. These methods are most suitable for equip-ment where testing is precluded by physical size of the equipment being qualified. It is required that, when these methods are employed, some partial type tests on vital compo-nents of the equipment be provided in support of these methods.

3. 0 MARGINS 3.1 Quantified margins should be For most plant specific applications, applied to the design parameters margins are available between the qual-discussed in Section 1 to assure ification parameters and the plant that the postulated accident con- specific requirements, ditions have been enveloped during testing. These margins should be Margins are as shown in the equipment applied in addition to any margins tables.

(conservatism) applied during the derivation of the specified plant parameters.

3.2 The margins provided in the design Same as 3.1.

will be evaluated on a case-by-case basis. Factors that should be considered in quantifying margins are (a) the environmental stress

levels induced during testing, (b) the duration of the stress, (c) the number of items tested and the number of tests performed in the hostile environment, (d) the per-formance characteristics of the equipment while subjected to the environmental stresses, and (e) the specified function of the equip-ment.

l EL40113W - 01/11/84 Rev. 1

m NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION

'3.3 When the qualification envelope in This generic envelope is not speci-Appendix C is used,.the only fically employed by Westinghouse or required margins are those account- Duke for qualification testing. It ing for the inaccuracies in the should be noted that a given manu-test equipment. Sufficient con- facturer's test curve may approximate servatism has already been included this generic curve.

to account for uncertainties such as production errors and errors associated with defining satis-factory performance (e.g., when cnly a small number of units are tested).

3.4a Some equipment may be required by In general, equipment required to oper-the design to only perform its ate in a harsh accident environment is safety function within a short time qualified to perform its safet.v function period into the event (i.e., within over a considerable period in excess of seconds or minutes), and, once its the calculated worst case time to perform function is complete, subsequent the safety functions as derived from the failures are shown not to be detri- accident analysis. The arbitrary ad-mental to plant safety. Other ditional one hour time requirement has equipment may not be required to not been applied to all equipment. The perform a safety function but must time margins indicated in the equipment not fail within a short time period tables are considered acceptable.

into the event, and subsequent failures are also shown not to be detrimental to plant safety.

Equipment in these categories is required to remain functional in the accident environment for a period of at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in excess of the time assumed in the accident analysis.

3.4b For all other equipment (e.g., In qualifying equipment required to post-accident monitoring, recom- operate in a LOCA, MSLB, HELB, or biners, etc.), the 10 percent post-LOCA recirculation radiation time margin identified in Section environment, margin is included in 6.3.1.5 of IEEE Std. 323-1974 may qualification testing by selecting be used. conservative qualification parameters and/or test sequences.

Some of the areas where margin is usually implicit in a test sequence is as follows:

1. The full radiation dose, simulat-ing effects of in-service and acci-dent radiation doses, is applied in a single step prior to seismic and HELB test simulations.

EL40113W - 01/11/84 Rev. 1

NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION

]

4 3.4b (Continued) (Continued)

2. The seismic event simulation applies significant mechanical stress to the equipment prior to the HELB simulation.

3. The single envelope normally employed for HELB simulation, not only encompasses the effects of LOCA and MSLB accidents, but a whole spectrum of break sizes and locations within these accident definitions. As a consequence, the envelope employed invariably contains significant margin with respect to the transient for any single break size and location.

4. The single HELB simulation normally employed combines the high irradia-tion dose associated with the LOCA with the high temperature associated with the MSLB.

4.0 AGING.

4.1 Qualification programs that are Safety-related valve operators (motor committed to conform to the and solenoid) located inside containment requirements of IEEE Std. 382-1972 and continuous duty motors located in-(for valve operators) and IEEE Std. side containment have been mechanically, 334-1971 (for motors) should con- thermally, and radiation aged sider the effects of aging. For in accordance with IEEE 382-1972 this equipment, the Category I and IEEE 334-1971, respectively.

positions of Section 4 are appli-cable.

4.2 For other equipment, the qualifi- Addressment of aging was not a require-cation programs should address ment in qualification programs for aging only to the extent that Category II equipment. However, with equipment that is composed, in the wealth of in-service experience part, of materials susceptible to covering a variety of equipment types, aging effects should be identified, no significant in-service aging mech-and a schedule for periodically anisms have been identified which could replacing the equipment and/or prejudice the qualification tests per-materials should be established. formed on new equipment within a few During individual case reviews, the years from start-up.

Staff wi11' require that the effects EL40113W - 01/11/84 Rev. 1

r NUREG 0588 CATEGORY II DUKE POWER COMPANY GUIDELINES POSITION 4.2 (Continued) (Continued) of aging be accounted for on selec- Inservice degradation is addressed ted equipment if operating experi- through preventative maintenance ence or testing indicates that the and surveillance programs with equip-equipment may exhibit deleterious ment and component refurbishment aging mechanisms. and/or replacement based on known susceptibility to aging degradation.

These programs are based on test results, manufacturer's recommendations, operating experience, and/or sound engineering practices. Additionally, EPRI research, NRC studies, NPRDS information, IE Bulletins and Information Notices, and industry research and testing will be used to augment this program.

5.0 QUALIFICATION DOCUMENTATION 5.1 The Staff endorses the require- Duke Power Company has arranged and ments stated in IEEE Std. 323- will maintain in an auditable form 1974 that, "The qualification sufficient qualification documen-documentation shall verify that tation that will support the quali-each type of electrical equip- fication that is required for each ment is qualified for its appli- type of safety-related electrica7 cation and meets its specified equipment.

performance requirements. The basis of qualification shall be explained to show the relation-ship of all facets of proof need-ed to support adequacy of the complete equipment."

" Data used to demonstrate the qualification of the equipment shall be pertinent to the ap-plication and organized in an auditable form."

5.2 The guidelines for documentation The qualification test reports in IEEE Std. 323-1971 are ac- referenced in the equipment tables ceptable. The documentation for equipment qualified to operate in should include sufficient infor- an accident environment, in general, mation to address the required meet the requirements of Section 5 information identified in Ap- to IEEE 323-1971 by providing certain pendix E. A certificate of con- essential information. For example:

formance by itself is not accept-dble unless it is accompanied - safety-related functional require-by test data and information on ments to be demonstrated I

the qualification program.

EL40113W - 01/11/84 Rev. 2 L

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

..c p NUREG 0588 CATEGORY II ~ DUKE POWER COMPANY GUIDELINES POSITION 5.2 (Continued)' (Continued)

- range of applicable environmental parameters to be considered

- identification of the test unit.

~

- description of the test facility and monitoring instrumentation

- description of test unit mounting and interfaces

- summary of the test procedures

- summary of the test results i

T I

r

)

'EL40113W - 01/11/84 Rev. 0

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

ML20093L526

Text

Subject:

Dear Ms. Adensam:

Conclusion:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY