ML20037C745

Forwards Proprietary & Nonproprietary Versions of Revision 2 of Response to NUREG-0588, Environ Qualification of Safety-Related Electrical Equipment. Proprietary Response Withheld (Ref 10CFR2.790).Affidavit Encl

ML20037C745
Person / Time
Site:	Summer
Issue date:	02/11/1981
From:	Nichols T SOUTH CAROLINA ELECTRIC & GAS CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML19260G583	List: ML20037C745
References
RTR-NUREG-0588, RTR-NUREG-588 NUDOCS 8102200400
Download: ML20037C745 (47)

Text

-

o SourH CAROLINA ELECTRtc a gas COMPANY 4

g

. w en a.o.,..

a

@g cotummia. sourw capotina asais B

P,

r. C. NogLs, JR.

pebruary 11, 1981

^

%p

,,u............,. c m n,

y

,m...:....,.,

g

'c l

s y.

j

-w i

Mr. Harold R. Denton, Director 9

[Nj Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Subj e,ct :

Virgil C. Su=mer Nuclear Station Docket No. 50/395 NUREG-0588 Revision 2

Dear Mr. Denton:

In our January 15, 1981 letter, South Carolina Electric and Gas Company (SCE&G) filed revision 1 to our NUREG-0588 response.

By this letter, SCE&G provides revision 2 to these documents. Also, one (1) copy of Westinghouse Affidavit CAN-80-31 (Non-Proprietary) is provided.

This revision updates information provided in the report.

As this submittal contains information proprietary to Westinghouse Electric Corporation, it is supported by an affidavit signed by Westinghouse, the owner of the information. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with spec ificity the considerations listed in paragraph (b)(4) of Section 2.790 of the Commission's regulations.

I Accordingly, it is respectfully requested that the information which is proprietary to Nestinghouse be withheld from public disclosure in accordance with 10CFR Section 2.790 of the Commission's regulations.

Correspondence with respect to the proprietary aspects of this application for withholding or the supportine Westinghouse affidavit should reference CAW-80-31, and should be addressed to R. A. Wiesemann, Manager, Regulatory and Legislative Affairs, Westinghouse Electric Corporation, P. O. Box 355, Pittsburgh, Pennsylvania 15230.

If you require any additional information, please let us know.

Very truly yours,

,/

./

T. C. Nichols, Jr.

I l

ND:RBC:TCN:rh cc:

Page Two 6 p@ l #

Mp0E i[

v,e M

- e

'81 0220 0%

A

i Mr. Harold R. Denton February 11, 1981 Page Two cc:

V. C. Summer C. H. Fischer T. C. Nichols, Jr.

E. H. Crews, Jr.

O. W. Dixon, Jr.

W. A. Williams, Jr.

O. S. Bradham D. A. Nauman R. B. Clary A. R. Koon A. A. Smith J. B. Knotts, Jr.

J. L. Skolds B. A. Bursey H. N. Cyrus

11. E. Yocom J. B. Cookinham NPCF/Whitaker File c

,s.

CAU-80-31 l

2 AFFIDAVIT CCMMONWEALTH OF PENNSYLVANIA:

ss COUNTY OF ALLEGHENY:

Before me, the undersigned authority, personally appeared Robert A. Wiesemann, who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Corporation (" Westinghouse") and that the averments of fact set forth in this Affidavit are true and correct i

to the best of his knowledge, infonnation, and belief:

hL

!Y11D44 Robert A. Wiesemann, Manager Regulatory and Legislative Affairs Sworn to and subscribed 4

befgre me this /<

day of ue 1980.

)

1 O'

%/

L(. M66 <

/wc,

Notary Public y

me:2

.e Mo.1 :esitte ' '.

% CA=1~n= r*

y,q.., h g -t m.*

. CAW-80-31 (1)

I am Manager, Regulatory and Legislative Affairs, in the Nuclear Technology Division, of Westinghouse Electric Corporation and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public dis-closure in connection with nuclear power plant licensing or rule-making proceedings, and am authorized to apply for its withholding on behalf of the Westinghouse Water Reactor Divisions.

(2)

I am making this Affidavit in conformance with the provisions of ICCFR Section 2.790 of the Commission's regulations and in con-junction with the Westinghouse application for withholding ac-comcanying this Affidavit.

(3)

I have personal knowledge of the criteria and procedures utilized by Westinghouse Nuclear Energy Systems in designating information as a trade secret, privileged or as confidential commerical or e

financial information.

(4) pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the in-fannation sought to be withheld from public disclosure should be withheld.

(1)

The information sought to be withheld frcm public disclosure is owned and has been held in confidence by' Westinghouse.

- t

y l

. CAW-80-31 (ii)

The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public.

Westinghouse has a rational basis for determining the types of information custcmarily held in confidence by it and, in that connection, utili:es a system to determine when and whether to hold certain types of information in confidence.

The application of that system and the substance of that system constitutes Westinghouse policy and provides the rational basis required.

Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential com-petitive advantage, as follows:

(a)

The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.)

where prevention of its. use by any of Westinghouse's competitors without license from Westinghouse consti-tutes a competitive economic advantage over other companies.

(b)

It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive econcmic advantage, e.g., by optimization or improved marketability.

r

4 CAW-80-31 (c)

Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.

(d)

It reveals cost or price information, production cap-acities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.

(e)

It reveals aspects of past, present, or future West-inghouse or customer funded development plans and pro-grams of potential commercial value to Westinghouse.

(f)

It contains patentable ideas, for which patent pro-tection anay be desirable.

i (g)

It is not the property of Westinghouse, but must be treated as proprietary by Westinghouse according to agreements with the owner.

There are sound policy reasons behind the Westinghouse system which include the following:

(a)

The use of such information by Westinghouse gives Westinghouse a competitive advantage over its com-peti tors.

It is, therefore, withheld from disclosure to protect the Westinghouse competitive position.

i

5-CAW-80-31 (b)

It is information wnich is marketaole in many ways.

The extent to which such information is available to competitors diminishes the Westinghouse ability to sell products and services involving the use of the information.

l l

(c)

Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.

(d)

Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage.

If competitors acquire components of proprietary infor-mation, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.

(e)

Unrestricted disclosure would jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition in those countries.

(f)

The Westinghouse capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage.

)

, CAW-80-31 (iii)

The information is being transmitted to the Comission in confidence and, under the provisions of 10CFR Section 2.790, it is to be received in confidence by the Comission.

(iv)

The information sought to be protected is not available in public sources to the best of our knowledge and belief.

(v)

The proprietary infonnation sought to be withheld in this submittal is appropriately marked infonnation provided to Westinghouse utility customers in WCAP-9745 entitled "Results of Westinghouse Review of Environmental Qualifi-cation References for WRD Supplied Category II Equipment with Respect to the Staff Positions in NUREG-0588" for their use in responding to the NRC request to review their qualification programs against the standards established in NUREG-0588.

This infonnation enables Westinghouse to:

(a)

Develop test inputs and procedures to satisfactorily verify the design of Westinghouse supplied equipment.

(b)

Assist its customers to obtain licenses.

Further, the information has substantial comercial value as follows:

(a)

Westinghouse can sell the use of this infonnation to customers.

1 j

, CAW-80-31 (b)

Westinghouse uses the information to verify the design of equipment which is sold to customers.

(c)

Westinghouse can sell testing services bas _d upon the experience gaired and the test equipment and methods developed.

Public disclosure of this information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to design, manufacture, verify, and sell electrical equipment for com-mercial power reactors without commensurate expenses.

Also, public disclosure of the information would enable others having the same or similar equipment to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the infonnation.

The development of the equipment described in part by the information is the result of many years of development by Westinghouse and the expenditure of a considerable sum of money.

This could only be duplicated by a competitor if he were to invest similar sums of money and provided he had the appropriate talent available and could somehow obtain the requisite experience.

Further the deponent sayeth not.

+e

-v-

1 l

1 l

VIRGIL C. SU. TIER NUCLEAR STATION O

r l

ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED j

l ELECTRICAL EQUIP!fENT/NUREC-0588 I

REVISION 2

)

l Instruction Sheet l

I I

i The following instructional information and check list is being j

furnished to help insert Revision 2 into the Virgil C. Summer i

Nuclear Station response to NUREG-0588 Discard the old sheets and insert the new sheets, as listed below.

Keep these instruction sheets in the front of the report to serve as a record of changes.

Remove Insert Title Page Title Page O

I il and ill lic Table of Contents Table of Content.n W-1 thru W-23 W-1 thru W-23 W-25 W-25 W-57 W-57 W-58 W-58 l

W-64 W-64 W-67 W-67 e

W-73 B-32a B-39a I

t l

O l

l

l i

e SOUTli CAROLIflA ELECTRIC & GAS COMPAtlY VIRGIL C. SUMMER tlVCLEAR STATI0fl 1

Envircnmental Qualification Safety Related Electrical Equipnent/flVREG-0588 I

Revision 2 I

WESTINCIIOUSE NON-PROPRIETARY DATA 1

!O

(W) positions have been established against the staff position for Category 11 equipment for the (W) scope of supply, based on the overall qualification q

methodology employed for this equipment.

O The review procedures for the B0P equipment were based on the design control program as documented in Chapter 17 of the FSAR and consisted of an adaptation of the existing procedures used for FSAR preparation. The source of all data and the results of the reviews were documented on individual worksheets. The completed worksheets, along with other supplementary material, were first re-viewed within the originating discipline. Then the material was reviewed by an interdisciplinary group.

For the fiSSS, a formal review and sign off was com-pleted by cognizant (W) management to meet quality assurance (QA) requirements.

THE BOP reviews by the architect / engineers and South Carolina Electric & Gas have confirmed that equipment installed in the plant is generally suitable for its intended use.

Problem areas have been primarily in the thoroughness of the tes t procedure docunentation.

In many cases, the test plans are not included in the qualification report, nor were detail data, such as, the accuracy of test instrumentation or the exact location of temperature monitoring thermocouples.

Additional details have been requested from the manufacturer and vendors.

In a limited number of cases the review has identified equipment which is adequate for its intended application, however, the available documentation does not support its contir.ued use under a particular environmental condition. To bring these into compliance with NUREG-0588, minor modifications have been identified.

These include changing some solenoid valves from normally energized to normally de-energized during LOCA and SLB, relocating some cables and conduits in Reactor Building for flooding and replacing Raychem high voltage stress relief termina tion on emergency feedwater pump motors and spray pump motors.

U Equipment categorized C,or C 1

2 in the NSSS tables is qualified for normal conditions and is not required to function following a steam line break or loss of coolant accident for mitigation of that accident. South Carolina Electric & Gas review for the NSSS included determining equipment location, identifying normal, abnormal and accidnet environmental parameters and design operability requirements under normal and accident conditions.

It also included reviewing Westinghouse quali-fication reports against NUREG-0588 positions, equipment interfaces against qualification configuration and confirming equipment qualified as equal to equip-ment in plant.

Documentation of the review of NSSS equipment compliance with NUREG-0583 is available in SCE&G's file. Our review shows generally that equipment qualification envelopes design basis accident conditions.

Problem areas have been primarily in documentation which does not include all necessary information such as location of temperature monitoring thermocouples, failure criteria or employing Cobal t 60 for gamma irradiation. Chemical spray concentration is not fully re-presentative of short-term plant specific conditions, however, it does represent the long-term condi tion.

Discrepancies with NUREG-0588 will be justified or the equipment will be upgraded or replaced.

Detailed reviews of the degrees of compliance with the criteria and interpreta-tions contained in NUREG-0588 ar compelted and this material is incorporated into revision 1 of this document.

In summary, all equipment installed in the V. C. Summer Nuclear Station is adequate for its intended use.

In a few minor instances where documentation does not fully support the application of equipment, action is being taken to correct the situation.

i a

ii Revision 2

TABLE OF CONTENTS O

Westinghouse Supplied Electrical Equipnent W-1 t hrough W-29 T abl es W-1 through W-29 Positions W-30 tbrough W-73 Balance of Plant Electrical Equipnent B-1 through B-216 Tabl es B-1 through B-74 Detailed Reports B-75 through B-216 Figures Figure 1 through Figure 34 O

oa 4537A

I NUCLEA SAFET EQUIPME TYPE IDCATION PODEL NLMBER ABNORMAL OR OF EQUIPMENT BUII, DING TAG NLHBER-MANUFACTURER IDENTIFICATick

ACCIDENT ENVIRONMENT 7 20)

Category-a2, c1 Ts Peak Temp.

Inte, Pressure Chemistry D-Hurai d i_.ty Condition Radi.

h

} a,e

~MSB Narrow Range RB, by TE-412 A,B,C,D Rosemount Resistance pass TE-422 A,B,C,D (T) FSAR (16) 6 73 >

Tempe r at ur e loop TE-432 A,B.C,D FIG. 6.2-5a Rac Detectors (P) FSAR FIG. 6.2-4 14CA (T) FSAR (16), (17), (18) 4.73 FIG. 6.2-7 Rad (P) FSAR FIG. 6.2-1

\\

l

i I

STEAM SUPPLY SYSTEM RELATED ELECTRICAL T INSIDE CONTAIN?iENT ENVIRONMENT TO WHICH QUALIFIED (14) jal Integrated iroted Peak Temp.

Dose Accuracy Accuracy Qualification e

Pressure Chemistry Radiation Operability Operability Requiremente Demonstrated Reference and tion Htsmi d i t y Conditi on Type Requiremente Demonstrated

(% of Span)

(! of Span)

Met hod (13) f.eer;ig.)a.s.c

[

1.2,...

a...e 3o.ac.

o.e, so

. 22 c

3a...

ecA,.,is, 10, 3

(5-3 and 6-3/

Acid and Post-SLB sec.

T8)

(8)

(Separate g

Boric Post-SLB Test) 0.17vt.%

a,b,c N,0H dissolved in ngo 7

10 W-1 Revision 2 i

i l

l l

l a

l l

w

(... _ _ _ _ _ _ _ _._..-.- -.._

. - -. - - =. -. - -..... ~ -.

i i

l I

l O

i i

i i

I i

i I.

l DELETE PAGE W-2, REVISION 1 1

i l

I i

i 1

i i

i i

i

)

3 i

l i

t a

u.

i r

6 i

O

l 1

\\

1 4

NUCLEAR 51 SAFETY RE TY ET.

IICAfl0N M)DF.L NUMBER ABNORMAL OR 0F EQUIPMENT BUILDING TAC NUM5F.R MANUFACTURER IDENTIFICATION ACCIDENT ENVIRONMENT T20)

Category-ag 52i7a; (2I)

I Peak Temp, Integratt I

Pressure Chemistry Dose Hinsidity Condition Radiatio i

]8sC g

Wide Range Re-RB, RCS TE-410, All, Rosemount g

sistance Tem-loop 420, 423, (T) FSAR (16) 2.4 x 10 4

j parature 4)D, 411 FIG. 6.2-5a Rads l

Detectors (P) FSAR l

FIG. 6.2-4

}

IX)CA (T)FSAR (16), (17),

2.4 x 10 FIG. 6.2-7 (18)

Rads

)

(P) FSAR l

FIG. 6.2-1 f

r I

i l

I 9

k I

l 1

i

5 a

lAH $UPPLY SYSTEM

AllD ELECTRICAL

)'il D( CONIAlhMi.NT ENVIRONMr.NT TO WH!rli OgAL1FirD (iW Integrated Peak Temp.

Dose Ac c urac y Accuracy Quellfication Presnore Chemistry Radiation Operability Operability R eq ui remen t s Demonstrated Reference and linni.f i t y C on<t i t '. un Type Requiremente Demonstrated (1 of Span)

(% of Span)

Method (IM

{(8)]a,b.c j

]a,bc WCAP-9157 e

1.146wt,t a,b,c 2 weent.

2.geks

+ 2g oee Borie Post-SLB Post-SLB

[8)

(by compari-son)

Fig. 5-3 Acid and and 6-1 0.17wt.I N OII a

~

]a,b,C dissolved in 11 0 j

2 i

l l

W-2 Revision 1 b

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

i 1

I i

NijCLEAR 51 SAFETY RE TTPE IJ) CATION M) DEL NtHBER ABNORMAL OR BUlt. DING TAC NUMBER MANUFACTURER iDENT!FICATION ACCIDENT FhVIRONMENT OF EQUIPMENT ~

~D O)

Cat egor y-c t, c 2 Total Peak Ternp.

Integrate Pressure Chemistry Dose Heidity Condition Raliatio 1 **C MSB Reactor Cool-RB FT-414, 415, 416 Barton (T) F5R 5 x 106

• J ant Fism DP FI-424, 42), 426 Transmitters FT-4 34, 4 3 5, 4 36 FIG. 6.2-ba (16)

Rads (5) (15)

(P) FSAR FIG. 6.2-4 IJ)CA 7

(T) FSAR (16), (17),

x 10 FIG. 6.2 7 (18)

Rads 4 months (P) FSAR 3

FIG. 6.2-1 9

i e

I I

i ti

!L

l l

l I

I t.ft sgal y 5,ST[M AllD [llCIMILAl

'51 b! LU4 T A l hMi 't f F_N V I.R O_N MF_N T_T_O 6 41CH_Qt' A1, f 5 f t h Int egr a t e.!

Peak Temp.

Doge Accuracy Accuracy Qualification

=

Pr e nier e Chemistry R 41i at ion Operability Operability bequirements Demonstrated Reference and gyni li t y con fi t i on Tvn Requirement

• fremons t r a t e d

(% of Span)

(% of Span)

Method g

Od (7)

(7) 139er Nane N me (11)

(11) 1 1

<1 1 Instruction Manual A r.,,-..i ph e r,,

(calibration 3,3 Test) (2)

W-3 Revision 2 e

v

(

0

\\

i;UCL TYPE LOCAT10N SAF MODEL NUMBER OF EQUIPMENT butLDING TAC NUMBER MANUFACTT!RER IDENTIFICATIOM ABNORMAL OR E0JIP

'~ff6T~~

ACCIDF NT ENVIRONMENT ~--

Category-ag, a2 Total Peak Temp.

Integra Pressure Chemistry Dose H ami di t y Condition Radiati Pressurizer RB PT-455, 456 Barton

]a,'

Pressure P 457 MSB Transattter"

( Lot 2)

(T) FSAR FIG. 6.2-5a (16) 3, 4 3 jg p

(P) FSAR FIG 6.2-4 LOCA (T)FSAR FIG. 6.2-7 (16), (17),

1.4 x 10 (P) FSAR II8)

Rads FIG. 6.2-1 4

4 i

i I

l l

l l

I 4

\\

\\

l

l l

1 l

i M <,I[ AM 5$ PLY SYS1!M TV WELAftD El[CTRICAL I

INT !!451D8 f.0td TAl f4fk N T F.NVIRONMENT TO Wit!CH QUAL.! PIED T14)

Integratrd 1

Peak Temp.

Doec Pressure Accut4cy Accuracy Qualification Chemistry Hah ation Operability Operability Regairements Demonstrated Reference and Homitity Conlition Type Re<piirements y

Demons

- -.trateel

( of S (I Of Span)

-. Method

_a bf 1.14wt.t d

Acid an!

]'h'C Trip Trip

+10; F

e,b.c Roric NS-TMA-2184 5 m.

5 m.

for Anderson to snd (Fig. 2. D --

0.17wt.%

i 5m.

Stolz Pos t -DB E N,OH (Sequential 4 ma.ith.

+

dissolved Teat) in water

~

l i

W-4 Revision 2

[

I a

J

/

i

r' 1

l 1

\\

\\

1 i

i i

i i

e NUCLEAR.,

SAFETY.

EQUIPMEM Tf PE IDC AfiON

11) DEL N1'MBER ABNORMAL OR OF tqu!PMfNT- ' ~ ~ ~

BullDINC TAG Nt'MBER MANUFACTURER IDENTIFICATION ACCIDENT ENVIRONMENT EU)

I2I) [

~

-( 2 () )

Category-al

, a2 I

Tota Peak Temp.

Integr; j

i Pressure Chemistry Los

)

Humidity Condition Radiat i

]a,c y

g Ftei wrtzer RB LT-459, 460, Barton ten.1 or 461 Lot 2)

(T) FSAR (16) 5y 10 tr m mitter.

FIG. 6.2-5a Radsi 41)

(P) FSAR FIG. 6.2-4 LOCA (T) FSAR i

(16), (17),

5 x 10' FIG. 6.2-7 i

(18)

Rads:

j (P) FSAR i

FIG. 6.2-1 l

1 I

l i

i l

?

J 1

V o

I c

f I

l l

l I

l l

i...,,..

n

]

5t!Ait St>PPLY SYSTLM FilAIED ELLCif(ICAL l Ife5!DE CuriTAlhMENT i

F.NVIRONMENT TO WH ICH __QUALIFI FD i.

(14)

{

int e gr at*4 2ei Peak Temp.

Dose Accuracy Accuracy Qualification j

Pregaure Chemistry Ha li a t ion Oper a bi li t y Opar tbility R*rsirements Demonstrated Reference and im Homi giit Condition

_Typ _e M uire'4ents Demonstrated (1 of Span)

J% of Span)

Method _

j

((J J (6)

(6) a,b,c 1.14wt.t a,b.c Post-DBE Pos t-DBE

~+25%

~

a,b,c NS-TMA-2184 Boric 4 monthe 4 months Anderson to l

_(Fig. 2.2) 0.17wt.1 Acid an1

~

Stolz (Sequential N OH Teet) dissolve in water j

i i

}

1 i

f I

i N*5 Revision 2 j

l l

1 9

'I l

i i

E

.-- =.-=..-- - - vemovwe.

_.ww--w-,-

,,_..eww-+...-w...,.,c w m

.m.

_ na

- ~ - - - - - - - - - -- - -

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

a 1

s I

i NUCL sAF TYFE IDCATION MDDEL NI'MBER ABNORMAL OR EQUIQ OF Equ!PMENT BUILDING TAG NtfMBER MANUFACTURER IDENT!FICATION

~ ACCIDENT ENVIRONMENT l

-(I6f--

Category-ag ud, a2 (2i}

Tots Peak Temp.

Integrj Pressure Chemistry Dos; Hinnidity Condition Ra dial

] a,c g

St e am Genera-RB LT-474, 475, 476 Barton for Level I.T-484, 485, 486 (Lot 2)

(T) FSAR Narrow Range LT-494, 495, 497 F20. 6.2-Sa (16) 5 x IQ DP Transmit-Radt p) 73gg FIG. 6.2-4 i

LOCA (T) FSAR 7

(16), (17),

5

• M i-FIG. 6.2-7 v

(gg)

(P)FSAR Rads FIG. 6.2-1 t

i i

1 t

1 i

9 e

1 I

P 5

I L

3

{

l

1 i

i PAR STEAM Sl!PPLY SYST[M

'TY RELATED LilCTRICAL ILNT MS!Dl CON?AlhMLNT l

l.

-F.NVIRONMF.NT TO Wit!Cil QUALIFIED

~T14) i Integrated e

'tel Peak Temp.

Dose Accuracy Accuracy Qualification Pr-seure Chemistry Radiation Operability Operability Requirements Demonstrated Reference and

,I of Span)

(% of Span)

Method

(

Hinnid git

~ Con-tition Type R ets i r eme n t s Demonstrated on

~Oli

~

(6)

(b)

Trip 5 m.

Trip 5 m.

+10%

~

~

** NS-TMA-2184 e,b,c 1.14wt.%

• • Sec

)

Baric and and

=

Anderson to l

Acid and

< 5 m.

stolz l

(Fig. 2.2) 0.17wt.%

Post-DBE Post-DBE 5 m.

(Sequential N,Oli 4 annths 4 months to 4 mo.

Test) i dissolved

-+25%

~

~

in water i

1 i

i I

W-6 Revision 2 i

l b

I

--....-.w

t I

\\

s NUI Si, TY Pt 14 CATION MODEL NUMBER ABNORMAL OR EQU' OF EtE1PME NT flu !!.D I NG TAG Nt'MBER MANUFACTURER ~

IDENTIFICATION ACCIDENT ENVIRONMENT

~

(20)

Category-a}

L'A3, a2 ( I}

Tot 4 Peak Temp.

Integr Pressure Chemistry Doc lbanidity Condition Radiat 4

J.

] a,e g

Reactor Cool-R5 PT-402, 403 Barton ant S y s t evu (Lot 2)

(T) FSAR Pres urr wite FIG. 6.2-5a (16) 5 x it 1

j R uze 4*

(P) FSAR Radf j

fran mitte-FIC. 6.2-4 l

j EA, (T) FSAR (16), (17),

FIG. 6.2-7 (gg) 5 x 10 (P) FSAR Rads FIG. 6.2-1 1

j I

l i

l I

l I

I s.

I I

1 I

L l

. EAR STEAM $UPPLY SV5 TEM

.ETY RELATED ELECTR! CAL HENT INSIDE CO'iTAINNENT ENVillONMP.NT TO MtICH QUALIFIED (14)

Integrated ted Peak Tmp.

Dose Accuracy Accuracy Qualffication Pressure Chemistry Radiation Operability Operability Requirements Demonstrated Refetence and Humi4tity Con <t i t i on Type Requirements Demonstrated

(% of Spen)

(! of Span)

Method yn (11)

~

"a,b,c 1.14wt.g

'a,b,e Post-DBE Post-DBE

+10%

a,b,e yg.TMA-2184 Boric 4 months 4 months Andereun to Acid and (6)

_(Fig. 2.2) 0.17 wt.!

Stola (Sequential)

N, Oil dissolved in water W-7 Revision 2 i

l l

{

l

J i

(

f TYPE IOCATION

!ODEL NLHBER ABNORMAL OR OF TQI'I PMENT BUILDING TAC NUMBER MANUFACTURER IDENTIFICATION ACCIDENT ENVIRONMENT f20)

Category-ct, c2 To 3,

j Peak Temp.

Intel Pressure Chemistry D

Hurnidi t y condition Radi

{(Lot a,c MSB Steam F1 w DP RB FT-474, 475 Barton 2)

(T) FSAR Traemitter FT-484, 485 j

Fr-494, 495 FIG. 6.2-Sa (16) 5x Rai (P)FSAR FIG. 6.2-4 LOCA (T) FSAR (16), (17),

5 x il FIG. 6.2-7 (18)

Radt j

(P)FSAR rtG. 6.2-1

\\

}

i I

i l

1 1

l

}

4 L

E f

l i

l I

\\

1 1

i

4 I

i u

i l

Ctf AR STEAf t SUPPLY SYSTEtt AFEfY RELATED ELECTRICAL

!PMEf4T IN5IDE CONTA!ht1ENT ENVIRONMENT TO W11tol QUALIFitD

.i

@)

al Integrated

ated Peak Temp.

Dose Accuracy Accuracy Qualification e

Pressure Chemistry Ra di at ion Ope-a b i li t y Operacialty Reqcirements Demonstrated Reference and g

i Con <lition Type Requirements Demonstrated

(% of Span)

(% of Span)

Metnsa i

qs,b,c Trip 5 m.

Trip 5 m.

-10%

m a,b.c 1

de e 1.14wt.%

NS-TMA-2184

)6 Boric and and

+ = for Anderson to 4

.(Fig. _2.2) 0.17 wt.%

Post-DBE Post-DBE 5 min.

(Sequentiel Acid and

< 5 min.

Stolz N,OH 4 months 4 months to 5 mo.

{

Test) dissolved

+25%

~ (6) 4 in water

[6)

~

l i

\\

1 I

I i

i i

4 I

i 1

1 l

l W-8 l

Revision 2 I

i i

t j

t t

i 1

i i

a

\\

lt i

NUCL SAF TY PE I.0C AT t oh MODEt. NUMBER ABNORMAL OR OUIE OF Ef)I?!P=4F NT Blf tt.nING TAG NtfMBFR MANUFACTtlRER IDENTIFICA TION ACCIDENT ENVIRONMENT

~ ^ ^ ^ ~ ' ~

RC Category-et, c2 Peak Temp.

Integrat Pressure Chemistry Dose Humidity Condition Radiatig P wer Ranga RB NC-41, 42, 43, Westingho'Jse

[

]a,c g

Nortpal Ope Neutron Detec-44 (T) FSAR Dose Rate enra. (i$)

FIG. 6.2-Sa (16) 9 9*7

• l0 "$

P)FSAR 4.5x10}o/

Therma FIG. 6.2-4 n

1,0CA Fast (T) FSAR 3

• IU "^

FIG. 6.2-7 (16), (17), camm.i (P) FSAR (18)

FIG. 6.2-1 l

I

)

)

w i

t l

i i

i I

i AP 51EA1 SUPPLY SYSTEf1 TY RELATED EllCTRICAL U4T INilDE C0NTAlfvENT 4

i ENVIRONMf NT TO 'a'li!CH Q11ALIFIED

( 14 )'

Integrated of Peak Temp.

Dose Accuracy Accaracy Qual;iication Pressure Chemistry Radiation Operability Operability Requirements Demonstrated Reference and Homidity Condition rype Requirements Demonstrated

(% of Span)

(% of Spani Met hoJ 7

'~'T [)V tine _

_a,b,c N/A N/A W Test 1/69 a,b,c N/A (4) 8 hr. at 1750F TSeparate nS Test) l4 n's 4

1

)

1 l

J 4

W-9

-l Revision 2 I

I

{

i I

1 5

b l

l 1

l

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

s a

k l

(

NUCLEA SAFET.

TY PE II) CATION MODEL NUMBER ABNORMAL OR OF EQUIPMENT BUILDING

~ TAG NtNBER MANUFACTURER IDENTIFICATION ACCIDENT ENVIRONMENT 7 20)

~

Category-ag, c2 Total Peak Temp.

Integra6 Pressure Chemistry Dose Hinnidity Condition Radiatia H yJ r oge n RB XP30004 A( 19)

Wes t ingha ase Electric Type A -

MSB Necombiner SHROOO4B(19)

Sturtevant Heat-r (ts)

(T)FSAR (16) 7.1 x 10 FIG.

6.,

Sa Rads c-(P) FSAR FIG. 6.2-4 LOCA (T) FSAR FIG. 6.2-7 (16), (17),

7.1 x 10 (P) FSAR (18)

Rads FIG. 6.2-1 1

ll l

I i

y 3

J l

1 i

f I

I 51EAM SUPPL) SYSTEM RELATED ELECTRICAL T IN5IDE CON'AINMENT l

t i

l ENVIRONMEN T TO WHICH Qt.fALIFIED l

l (14) l Integrated i,1 Peak Temp.

Dose Accuracy Accuracy Qualificatino l

Pressitre Chevels t r y Railarinn Operability Operability Requirements Demonstrated Reference and Hinidi t y Condition Type Requiremente Demonstrated (t of Span)

(1 of Span)

Method

~@I 7

a,b,e 2500 ppm h

a,b,e 1 yr.

I yr.

N/A N/A WCAP-7820 and f

Boron as i

Post-LOCA Post-LOCA Supp. 1-4 j

Boric \\c{d WCAP-7709-1

)

_(See Supp.

with N 0H a7d Supp. 1-4 j

3 i

7 Sect.

to give a (Separate 1

3.4. 3) pH of 10 Test) i

}

l t

}

I l

I i

1 i

1 i

I i

u-10 Revision 2 l

1 l

6 r

--a

..mu__.._m.-m___m_m I

(

i l

q NUCL; SAf[

TY PE LOCATION MODEL NUMBER ASNORMAL OR u F, F 90 ! PM.E NT

.R.U 11.D I NG TAG Nt'MBER MANt'F ACTt'R F R IDENTIFICATION ACCIDENT ENVIRONMENT Total Peak Temp.

Integrate Radiatio Pressure Chemistry Dose Hinsi di t y Condition l

Valve Motor RB 8112 Limitorque a,c ggg l

(T)F5R 7.1 x 10 op ritora

,16) s FIG. 6.2-Sa Rads inc h close (P) FSAR FIG. 6.2-4 LOCA (T) FSAR (16), (17),

7.1 x IC FIG. 6.2-7 (18)

Rads g

l (P) FSAR FIG. 5.2-1 j

4 i

I l

t 1

(

?

i i

(

I i

i e

i I

}

l t

l AR STEAM SLPPLY SYSTEM

-lTV RELATED FLECTRICAL INT INSIDE CONTAINt!ENT ENVIRONMENT TO Wilicil Qt'ALIFIED (14)

Integrated 3

Peak Temp.

Done Accuracy Accuracy Qualification j

Pressure Chemistry Radiition Operabili t y Operability Requirements Demonstrated Reference a n -1 Humi d i t y Cond{ tion Type

~~julremente Demanstrated

(% nf Span)

(% af Span)_

Met hM Re 3DV p

qa,b,c

_.,b,e 2500 ppm i

! year 2000F N/A N/A WCAP-7744 i

Borie Acid l

~

Post DBE for 30 dayr*

WCAP-7410 4

buffered NS-CE-692 l

with 0.24%

(Test)

}

N OH a

I i

t

• NO TE : This test was not intended t o demonst r.ite post-DBF. thermal aging, it however, does demonstrate post-DBE operability i

consistent with the recommendatione of IEEE-382-1972 j

l W-11 Revision 2 l

l l

I i

9 s

l

4

\\

o l

NUCLEAR SAFETY EQUIPMENT

4) DEL NLMBER ABNORMAL OR TY PE thCATION

~

(20) -

TAG NLHBER_

MANUFACTURER IDENTIFICATION ACCIDENT ENVIRONMENT OF EQUlPMENT BUILDING Category-al, c2 I

Total-Peak Temp.

Integrati t

Pressure Chemistry Dose H umidi t y Condition Radiatio' 4

~

valve Motor ER 8701 A, B; Limitorque

' C g

Orcrators 8702 A, B (T) FSAR 6

(16) 7.1 x 10 FIG. 6.2-5a Rads v.31 v, s (P) FSAR 12 in. Gate FIG. 6.2-4 LOCA (T)FSAR

,16), (17)' 7.1 x 10 FIG. 6.2-7 gg3)

Rads (P)FSAR FIG. 6.2-1 1

1 k

i t

[

1

)

l l

l l

l l

l liEA!1 SuitLY $YSTEM l ELATED ELECTRICAL If451DE Coli1Alf4 met 4T l

FNVIRONMENT TO WHICH QUAL,IFIED 7 14)

Integrated i

Peak Tamp.

Done Accuracy Accuracy Qualification Pres.ure Chamistry Radiation Operability Operability Requirements Demonstrated Reference and tsirements Demonstrated (I of Span)

(% of Spaq)

Met hod Hutni di ty Condition Type Re 7 tit 3a,b,c

! year 200 F for N/A 11/A WCAP-7744

-4,b,c 2$00 ppm y

WCAP-7410 0

Boric Acid j

Post DBE 30 days

• NS-CE-692 buffered (1est) with 0.24%

N OH a

• No11: This test was not intended to demonstrate post-DBE thermal aging, it however, does demonstrate post-DBE operability consistent with the recommendations of IEEE-382-1972 W-12 Revision 2 l

4

W l

NUC.

SA:

EQUI:

TY PE IDCAf!ON MDIL NUMBER AB90RMAL OR OF EQUIPMENT BUII. DING TAG N"MBVk MANUFACTLRER IDFh'!FICATION ACCIDENT ENVIRONMEst

'~~

~~I2Ol~~

Category-ag, a2

[( l Peak Temp.

Inte Pressure Chemistry D'

H umi di t y Condition Radi.

2 i nc h G lobe RB 8149 A, B, C ASCO

_ ]a,c usg vstves salenoid" (T) FSAR (16) 6.6 FIG. 6.2-ba Ra (P) FSAR FIG. 6.2-4 LOCA (T) FSAR (16)

(ggy' (17)'

FIG. 6.2-7 6.6 (P) FSAR Ra FIG. 6.2-1 f

I 1

I s

E 1

I e

$< '31! Ali '.A H y ', t l i M T k(( AILD illCIR!LAL if INil' [ Uni AlhML U

---

. N T.-

TO 'a'H.I.CH Qt ' A_1. l F I E D.

VN V i kON9 Integrated tel l'e a k T emi p.

Ome Accuracy Accuracy Qualification pressure C he n.i n t r y R a ii a t i an Oper sb i li t y Ope ra b i l i t y Requirements Des,nstrate.1 Reference and H y(i.j,i t,y Con <t i t i nn Typ*

R egi:i r ema n t s Demonstreted (I of Span)

(I of Span)

Met hod on 1))

_" ' I' ' C 1.2%

8+b,c Trip 1. 5 m.

Trip (1 br.

h/A N/A NS-CE-755

()4 P.> r i c Acid (Analysis) 0" W-13 Revision 2

l P

1 i

4 i

l i

i l

I I

N!

l 5

EQL TYPE U) CATION PODEL NUMBER ABNORMAL OR j

OF EQUIPMENT BUILDING TAG NUMBER MANUFACTUltER IDENTIFICATION ACCIDENT ENVIRONMENT (20)

Category ag, a2 T<

j Peak Temp.

Inte Pressure Chemistry D

i f

l'umidity Condition Radi q

l inch Globe RB 8154 ASCO valve Solenoid (T) FSAR

}

FIG. 6.2-5a (16) 6.6 p,

(P) FSAR 4

FIG. 6.2-4 LOCA (T) FSAR (16), (17).

6.6 FIG. 6.2-7 (18) m (P) FSAR FIG. 6.2-1 i

f 4

1 l

I a

'l i

\\

?

l i

4 i

L_.

s e

i i

I f

i f

I l

EAR Sif All SUPPLY SYSTEM ETY HELATED ELECTRICAL 31LNT INSIDL LONTAlhMINT DiVINONMENT TO Wit!CH ({AI.1FIED (iW~

l Integrated r c <l Peak Temp.

D.>a e Accuracy Accuracy Qualification Pressiere Chemistry Radiation Operability Operability Req u i remerit s Demonstrated Reference and H.im i.li ty Con.fition

_ Type Requirements Demonstrated

(% of Span)

(% of Span)

Method on (tit

_a,b,c 1.2%

a,b,c Trip 1.5 m.

Trip 1 br.

N/A N/A NS-C E-7 5 5 4

30 Boric Acid [

(Analysis) 10

4 i

I 1

I l

1 1

J I

W-14 Revision 2 i

I Ii

l NU TYPE IDCATION MODEL NUMBER ABNORMAL OR EQUI OF EQUIPMENT BUILDING TAC NtHBER MANUFACTURER IDENTIFICATION ACCIDENT ENVIRONMENT 7 20)

Category-al, c2 Total Peak Temp.

Integra2 Pressure Chemistry Dos e Himi di ty Condition Radiatig Sole]noid a,c g

i inch Globe RB 8153 ASCO valve g p5g FIG. 6.2-ba Rads (P) FSAR FIG. 6.2-4 LOCA (T) FSAR (16), (17),

6.6 x 10 FIG. 6.2-7 (18)

Rads (P) FSAR FIG. 6.2-1 l

I

A i

1AR STEAff $UPPLY SYSill1 ETY RELATED ELECTPICAL NfNT IN51DE C0'iTAINMLhi ENVIRONMENT TO WHICH QUALIFIED (14)

Integrated

)d Peak Temp.

Dose Accuracy Accuracy Qualification Prensare Chemi s t ry Padiation Operability Operability Requiremente Demonstrated Reference and g

insidity Conditi3 Type Requiremente Ectnons t ra t ed

(% of Span)_

(%_of Span)

Method CDT

~

~.i,b,c 1.2%

{

a,b c Trip 1.5 m.

Trip <1 hr.

N/A N/A NS-CE-755 5

Beric Acid {

(Analysia) f W-15 l

Revision 2 l

i

J 1

l 1.

I I

t l

NUCLEAR J

SAFETY TY PE LOCATION MODEL NUMBER ABNORMAL OR j

OF FQUIPMENT BUILDING TAC NUMBER MANUFACTURER IDENTIFICATION ACCIDENT ENVIRONMENT i

(20)

Category-ag, c2 Tr.a{

}

Peak Temp.

Ip'.e graf Pressure Chemistry Dose Humidity Condition Radiatij 3 inch Globe RB LCV-460, LCV-459 ASOG a,c HSB Vsive Solenoid (T) FS2R FIG. 6.2-5a (16) 6.6 x 1@

Rads (P) FSAR FIG. 6.2-4 LOCA (T) FSAR (16), (17),

6.6 x 1 FIG. 6.2-7 i

(18 Rads (P) FSAR FIG. 6.2-1 t

f i

t i

I i

i f

I t

a I

I i

k i

I l

i

\\

.-m

Ii

-1EAM SUPPLY SYSTEM

.ELAftD ELECTRICAL

.INSIDE LONTAINMENT

~F.NVf RONMENT TO b4t!CH Qt?AI.!FIED

[14) 1 Integrated 41 Peak Temp.

Pase Accuracy Accuracy Qualification P r a s s iste Chemistry Raliation Operability Operability Reqsirements Demonstrated Reference and

~(U)

' Demonstrated

(% of Span)

(% of Span)

Method H eid jit Condition Type Requirements

~

• a,b,e 1.2%

a,b.c Trip 1.5 m.

Trip <1 br.

N/A N/A NS-CE-755 Boric Acid (Analysia)

W-16 Revision 2 I

i i

I

)

i4UCLE SAFE TYPE IDCATION mDEL NUMBER ABNORMAL OR EQUIFt4 OF t.QUlPMENT Pff!LDfNC TAC NUMBER MANUFACTURER IDENTIFICATION ACCIDENT ENVIRONMENT (20)

Category-ag, c2 Total Peak Temp.

Integrate Pressure Chemistry Dose munidity Condition Radia t ioit 2 inch Clube RB 81?.5 ASCO a,e g

Valve Solenoid (T)FSAR 4

(16) 6.6 x 10 FIG 6.2-Sa Rads (P)FSAR FIG. 5.2-4 LOCA 5

(T)FSAR (16), (17),

6.6 x 10 FIG. 6.2-7 (18)

Rads (P) FSAR FIG. b.2-1 l

i --. - - -

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

)

1

+

j I

i

(

i l

i 4

(

f.R Sli All SUPPLY Snif ft f

i

't REL ATE D ELICTRICAL l

t

NT IfiSIDL LONIA!!if% NI

)

~~~ ENVIRONMENT TO Wit!Cif QUALIFIF D l

(143

~~

[

i Integrated 5

3 Peak Temp.

Done Accuracy Accuracy Qualification

[

Pressure Chemistry Radiation Operability Operability Re<1uirements Demonstrated Reference and i

I Humidity Cond i t i on Jpe Requisemonte Demonstrated

(% of Span) f% of Span)_

Met hod l

TfD l

1 4,b,c 1.2%

a,b.c Trip 1.5 m.

Trip <1 hr.

N/A N/A NS-CE-755 Boric Acid (Analysis)

I j

l t

i

}e i

i l

i i

T f

t 1

i i

i 4

tf i

i i

i i

W-17 Revision 2 i

f I

i 6

i

t t

I I

NUCLE SAFE TY PE LOC ATION MODEL NLHBER ABNORMAL OR EQUIPM OF FQ191NENT Bi'!! DING TAC NUMBER MANUFACWRER IDENTIFICATION ACCIDENT f.NVIRONMENT

~

7 fd F Cate[ory ag, c2 Total Peak Temp.

Integrat Pressure Chemistry Dose Minidity Condition _

Radiatic-

] #

S I

=-h RB 8047 ASCO solenotd U " * *'

(T)FSAR (16) 6.6 x 1 FIG. 6.2-La Rads (p) FSAR FIG. 6.2-4 LOCA (T)FSAR (16), (17),

6*6 x 1 FIG. 6.2-7 (gg)

Rads (P)FSAR FIG. 6.2-1

\\

(

f i'

i h,

I f4

?,

i

(

t' f

i M STEAli SUPPLY SYSTEf1 i

Y RELATED ELECTRICAL r

'f4T INSIDE CONTA!f4 MENT I

ENVIRONMEN T TO WlICH QUALIFIED f

l (141

(

Integrated Accuracy Accuracy Qualification Dose

'd Peak Temp.

l Pressure Chemistry Radiation Operability Operability Requirements Demonstrated Reference and e

Humidity Condition Type Requiremente Demne t ra t ed

(! of Span)

(% of Span)

Method e

i N

4,b,e Tr p 1.5 m.

Trip <1 hr.

N/A N/A NS-cE-755

"'h c

1.2%

k (Analysis) e Boric Acid i

h 1

1 1

I.

i t

i i

(

)

i 1

W-18 Revision 2 1

i f

i

),

1 1_ _

6*

r w

i i

NUCLEl SAFE 1 EQUlFMI TY Ph IDCATION M) DEL N!'MBER ABNORMAL OR OF Ff>P! PME NT BUILDING TAG NINBER MANUFACTt!RE3 IDENTIFICATION ACCIDENT ENVIRONMENT

'~~

7 20s Category ag, c2 Total Peak Temp.

Integra Pressure Chemistry Dose Hwnldity Condition Radiatl

{ ] a.c M3B 1 inc h Globe RB 8075 A' 0' (T)F5R valve Solenoid (W

6.6xH FIG. 6.2-s,o Rads (P)FSAR FIG. 6.2-4 LOCA (T) FSAR (16), (17).

6.6 x 1 FIG. 6.2-7 (18)

Rads (P)FSAR FIG. 6.2-1 i

4 i

I l

l l

I l

l 1

1 d

I i

I

L-,

R STEAt1 LUPPLY SYSTEM y RELATED ELECTRICAL iT INSIDE LONTAINMENT I

j t.NVIRONMF.NT To WHICH QUALIFIED j

(14)

Integrated led Peak Tem p.

Dose Accurscy Accuracy Qualification

}

Pressure Chemistry Rafiation Operability Operability Requirements Demonstrated Reference and

'.n Humidity Conditinn Ty pe Requiremente Demonstratfd

(% of Span)

(% of Span)

Method (13)

I

~

a,b,c g,2g l

{

'a,b,e Trip 1.5 m.

Trip <1 hr.

N/A N/A NS-CE-755 Boric Acid l

(Analysis) l l

l b

l l

r l

l I

W-19 l

Revision 2

(

l i

d E

y i

1 i

f

(

A 4

k.

1 l

\\

't E Q' TYPE IDCATION TDEL NUMBER ABNORMAL OR i4 {y:'I PwE NT BUILDING TAG NUMBER _

MANUFACTURER IDENTIFICATION ACCIDENT ENVIRONMENJ (10)

Cat egc ry-ag, c2

'1 Peak Temp.

Intt i

Pressure Chemistry I

Wuni di t y Condition Rg

{

1/'+ inch Globe RB 8671 ASCO a,e Valve Solenoid (T) FSAR (16) 6.6 FIG. 6.2-Sa R4 (P) FSt.2 FIG. 6.'i-4 UN (T) F5AR (16), (17)

FIG. 6.2 7 (gg)

(P) FSAR FIG. 6.2-1 i

i 4

1

~

t i

~

i J'

~e s

)

f

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

v h

l t

r l

P l

t l

l 6

f ItA STEiJ4 SUPPLY SfSTEH ITY PEL ATED ELECTRICAL hiN1 INSIDE CONTAINMENT FNVINONMENT TO Wi!TCH Qt3ALIFIFD (14) j.

I integrated ted Peak Temp.

Dose Accuracy Accuracy Qualification [

Pressure Chemist y R a lia tion Operability Operability Requirements Demonstrated Reference and l

~

H.anJ di t y Condition Type Req'airemente Demonstrated (I of Span)

(I of Span)

Method an (ii) a.b,c 1.2%

a,b,e Trip I.5 m.

Trip <1 hr.

N/A N/A NS-C E-7 5 5 4

g Boric Acid (Analysie)

I N

iO i

+

f t-i I

[

I U-20

[

Revision 2 e

?

I t

J e

i

i t

t

)

lV A

J g

y J

• ?. '. ",

4;

- 4"

.,-c,

- + -

.L

--v,,

r,

,r-

. -~.

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

l i

j i

-; r 7

\\..

l r

i l

I huCL~

(

SAF:

EQUIPa i

f TiPE IDCATIO*i -

!ODEL NUMBER ABNORMAL OR 0F EQUIPMENT BUILDING TAG NUMBER MANUFACTURER IDENTIFICATION ACCIDENT ENVIRONMENT j

(20)

Category-ag, c2 i

Tota 4

Peak Temp.

Integre Pressure Chemistry Dose Humidity Conditi on Radiati

]a,c M, SB 3 inch Clote RB LCV-1003 ASCO V*I" Solenoid (T) FSAR (16) 6.6 x 3 FIG. 6.2-Sa Rads-l (P) FSAR i.

FIG. E.2-4

.i LOCA I

(T) FSAR (16), (17),

6.6 x 1.

FIG. 6.2-7 (18)

Rads (P) TSAR FIG. 6.2-1

=r

+

4 i

D 4

Y 5

I s

/

si

.l-

. ~.. =__-

- - _ - _ - ~,.

i 1

1 7

.AR STEAff SUPPLY SYSTEf1 TY kELATED ELECTRICAL y

ENT INSIDE C04TAINME!4T i

8 i

F.NVIRONMENT TO WHIOl QUAI.IFIED (14)

Integrated

.c.i frak Temp, Dose Accuracy Accuracy Qualification Pressure Chemistry Radiation Opetat ili ty Operability Requirements Dem ms t ra ted Reference and n_

liiuni d it y Condition Jp_e Requiremenp Demonstrated (1 of Span)

(% of Span)

Method (13) a,b,c 1.2:

a,b,c Trip '.5 m.

Trip <1 br.

N/A N/A NS-CE-755

)4 Boric Acid (Analysis) t L

~

W i

• 6 i

1 4

J 1

V I

i i

W-21 Revision 2 I

i i

I i

t t

4 t

n 1

I NU(

SA 1Y PE IDCATION MODEL NUMBER ABNORMAL OR OF EQUIPMENT BU lt.D I NG TAG NUMBER MANUFACTURER IDENTIFICATION ACCIDENT ENVIRONMENT (20)

Category-ag, c2 Tota l

i Peak Temp.

Integra Pressure Chemistry Dose i

Htanidi ty

.C.r. li t i on Radiatil l

]a,c g

3/4 inch Globa RB 7126 ASCO Valve solenoid (T) FSAR (16) 6.6 x IC FIG. 6.2-Sa Rads I

(P)FSAR FIG. 6.2-4 Lom i

1 l

(T) FSAR (16), (17).

6.6 x 11 FIG. 6.2-7 (18)

Rads i

j (P)FSAR i

FIG. 6.2-1 4

l

}

l i

i 1

i i

l i

l l

i t

I I

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

i E

, EAR STEAM SUPPLY SYSTEM IETY RELATED ELECTRILAL

' MENT INSIDE CONTAINMENT ENVIHONMENT TO WillO! QlfALIFIED (14)

Integrated ed Peak Temp.

Dose Accuracy Accuracy Qualification Pressure Chemistry Radiation Operability Operability Requirements Demonstrated Reference and

~

Ibemi dit y Condition Type Retairementa Demonstrated

(% of Span)

(% of Span)

Method n

~O 3) a,b.c Trip 1.5 m.

Trip <1 hr.

N/A N/A NS-CE-755

.i, b, c g,2%

0 Boric Acid (Analysis) w fJ W-22 Revision 2 i

i I

i i

I i

l i 9 4

l J

+

i I

DELETE PAGE W-23, REVISION 1 i

i I

O

.- J

\\.

I sac SA EQUI fy } E IJ x:A r !(.N Pf )l)F.1, N1'MHP.H ABNiiRMAL OR Af. f l_)FN r F NVIRONMENT y

t if 'I PMt N T H M !!.fil Ns; 1 Af; N!'MB> R MAN!!F ACTt'R t R ll)f NilF1(:ArroN t

t4

(,. g [

Cat e gor y-41, c t Peak Temp.

Integr Freneure Chemistry D<,s liomility Con,li t i on Raliat

.i..m m int 1 sh fl16 M10ln.

NA WO A'C

{B, I. i.n i t ; wit.het M10?A, Mo41 (T) f SM (g) il

" I ' ^ ', 0 IIG. 6.2-La PM

"' C t.cv -.#

tcv-459 (p) g5gg sn it, Pcv 44'.n I. 6.24 rev 4'.5 A, Pcv 445n I.OCA 1

(t)ISAR

( p, ), (17),

6.1 mi Rad I!G. 6.2-/

(18)

(P)ISAR FIG. f,.?-l 1

1

(

I

\\

.~.

~.. _..

f

(

l STEAM SUPPLY SYSTEM RELATED ELECTRICAL fil INSIDE CONTAINMENT ENVIRONMENT TO WHICH QUALIFIED (14)

Integrated 41 Pesk Temp.

Dose Accuracy Accuracy Qualification Pressare Chemistry Radiation Operability Operability Requirements Demonstrated Reference and Ennidity Condition Type Requirements Demonstrated

(% of Span)

(1 of Span)

Method (13) a,b,e A Mixture a,b,c 1 year 2000F for N/A N/A NAMCO G

0 of Boric Post-DBE 30 days *

. Test Report

~

Acid, Water

~

~

(Revision 1)

Sodium 9/5/78 Thisolfate, (Test) and Sodium Hydroxide with a pH of between 10 and 11.

7

• QTE : This test was not intended to demonstrate post-DBE thermal aging, it however, does demonstrate post-DBE operability consistent with the recommendations of IEEE-382-1972 W-23 Revision 1

u.

i (15)

Equipment that could experience environmental conditions of design s

basis accident (SLB or LOCA), through which it need not function J

for mitigation of accidents, and whose failure is not detrimental to plant safety or accident mitigation, and need not be qualified for any accident environment, but iu qualified for non accident service envrionment.

See table 3.11.3 of FSAR for normal environ-ment.

(16)

For 47 minutes at 40*F to 120*F the spray consists of demineralized water containing 1950 ppm to 4000 ppm born in the form of boric B0 ) and llaOH (.68% by weight Pil ranges from 10 to 10.7),

acid (II3 3

see FSAR figures 6.2-51s,followed by a solution Pli of 8.7 ( 23% by weight) for approximately 73 minutes.

(17)

For the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> at 240*F the spray consists of demineralized water contain 1730 ppm to 3500 ppm boron in the form of II3B03 and N 011 (0.23% by weight) at a pil of 8.7.

a (18)

For the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 190*F, the spray has the same constituents as described in 17, above.

(19) Virgli Summer identification number.

l l

(20)

Refer to Table 3.11-3 for associated postulat ed environmental conditions.

(21)

Post accident monitoring only.

O W-25 Revision 2

WESTINGHOUSE SUPPLI2 k

i EQUIPMENT MODEL BARTON BARTON

(" p,c LOT 2 TRANSMITTER TRANSMITTERS QUALIFICATION DOCUMENTATION INSTRUCTION NS-TMA-2184 REVIEWED MANUAL NUREG-0588 Item 2.1.

(1)a NA A

(1)b A*

NA (2)

NA (A)

(3)

NA A

(3)a NA A

(3)b NA A

(3)c (4)

NA (4)

NA NA 2.2.

(1)

NA A

(2)

NA A

(3)

A*

A (4)

NA A

(5)

A (2)

(6)

NA A

(7)

NA A

(8)

NA A

(9)

NA A

(10)

NA A

(11)

A A

(12)

NA A

2.3 (1)a (5)

NA (1)b NA A

(2)

NA A

(3)

A*

A (4)

(4)

A 2.4 NA A

3 (1)

NA A

(2)

NA (3)

(3)

NA A

(4)a NA (1)

(4)b NA A

4 (1)

A*

A (2)

A*

A 5

(1)

A*

A (2)

A*

A

• Per IEEE Standard 323-1974 f.

7937A

I

~

l TABLE 1 EQUIPMENT LOCATED INSIDE CONTAINMENT LIMITORQUE l

[

]a,c ROSEMOUNT RELIANCE MOTOR RTD's OPERATORS WCAP-7410 WCAP-9157 NS-CE-692 A

A NA NA (6)

A A

A A

A A

(12)

NA (12)

NA NA A

A A

A A

A (7)

A A

A A

A A

A A

A A

A A

(17)

A A

A A

NA NA (7)

(15)

A A

A A

A (15)

A A

A A

A A

A A

(7)

A A

A A

A l

A A

l A

A l

A A

W-57 i

Revision 2 l 1

k

(

WESTINGHOUSE SU EQUIPMENT MODEL NEUTRON DETECTORS QUALIFICATION DOCUMENTATION W TEST REVIEWED 1/69 NUREG-0588 I tem 2.1.

(1)a NA (1)b A

(2)

NA (3)

NA (3)a NA (3)b (9)

(3)c NA (4)

NA 2.2 (1)

NA (2)

NA (3)

A (4)

NA (5)

A (6)

NA (7)

NA (8)

NA (9)

NA (10)

NA (11)

A (12)

NA 2.3 (1)a (10)

(1)b NA (2)

NA (3)

A (4)

(9) 2.4 NA 3

(1)

NA (2)

NA (3)

NA (4)a NA l

(4)b NA l 4

(1)

A l

(2)

A 5

(1)

A (2)

A f

f 7937A

TABLE 1 ( Cont.)_

f f

' LIED EQUIPMENT LOCATED INSIDE CONTAINMENT

{.

HYDROGEN RECOMBINER ASCO SOLEN 0 IDS (MODEL A)

[

]a,c WCAP-7709L NS-CE-755 A

(11)

NA NA A

(11)

A (11)

A (11)

A (12)

NA (12)

NA NA A

NA A

NA A

NA (8)

NA A

NA A

NA A

NA A

NA A

NA (16)

(17)

A A

A NA NA NA (8)

NA A

NA A

NA A

(11)

A A

A A

(8)

(13)

A A

A (13)

A NA (8)

A (8)

A A

A A

NA W-58 Revision 2 l

l

14.

DELETED.

O l

4 i

i 15.

No single reported test sequence included both [ radiation and chemical spray]b,c,e.

However, one of the units employed in the 1972 series of tests had previously been exposed to [ radiation, a seismic test and a steam / chemical] b,c.e envi ronment.

The successful retesting of this unit demonstrates that this model of l

operator is not marginal with respect to any of the qualification parameters.

I The original NRC review of WCAP-7410 resulted in a request for additional infomation concerning these operators, contained in an

]

NRC evaluation letter; Vassallo to Eiche1dinger dated March 12, 1974. As a result Westinghouse submittals NS-CE-692, 756 and 847 provided the requested infomation.

An internal Staf f review of 4

this material (Ref 5) concluded that the environmental test results for MOV's utilizing type H or HR insulation were acceptable.

16.

The hydrogen reccmbiner qualification to simulated LOCA conditions was complH ed employing varying electrical power levels to verify functional performance, as reported in WCAD-7709-L.

17.

Suf ficient difficulty exists in monitoring the performance of i

equipment exposed to the rapidly changing adverse enviroment gen-erated by a HELB that applying variations to the electrical supply concurrently could mask the true performance of the equipment.

l Westinghouse believes that the requirement for operation at the lO extr-es of nower sunniy voite9e end frequency must be reco9 aired W-64 Revisioni i

7937A

J WESTINGHOUSE SUPPLIED [

(

QUALIFIED FOR R LIMIT 05 ASCO SOLEN 0 IDS,

[

EQUIPMENT MODEL

[

] '

MOTOR 0 QUALIFICATION LIMIT 0' DOCUMENTATION REPORT:

REVIEWED NS-CE-755 DATED ;

NUREG-0588 I tem 2.1. (1) a (1)

(5)

(1)b f%

NA (2)

(1)

A (3)

(1)

A (3)a (1)

A (3

(3)b (3)

(3 (3)c (3)

(4)

NA NA-2.2,(1)

NA A

(2)

NA A

(3)

NA A

(4)

NA A

(5)

NA A

(6)

NA A

(7)

NA A

(8)

NA A

(9)

NA A

(10)

(4)

(41 (11)

A A

(12)

NA A

2.3.(1)a NA NA (1)b NA A

(2)

NA A

(3)

NA A

(4)

(1)

A 2.4.

A A

3 (1)

A A

(2)

(2)

A (3)

A A

(4)(a)

(2)

A (4)(b)

NA A

4 (1)

A A

(2)

A A

5 (1)

A A

(2)

NA

'A l

(

7937A

L, l

TABLE 2 i

I

%IPMENT LOCATED OUTSIDE CONTAINMENT t

$ VERSE ACCIDENT ENVIRONMENTS

/

j 1

lQUE PUMP MOTORS BARTON l

],, c USED FOR LOT 2 fERATORS RECIRCULATION TRANSMITTERS (NE DESIGN SPEC.

WO B0003 AND

/7/76 WCAP 8754 NS-TMA-2184 (S)

Table 1 NA Assessment (6) is applicable A

A

. NA NA NA A

A A

(7)

A NA NA NA NA (4)

A A

NA (6)

A A

NA (6)

A (7)

A A

(7)

A A

A A

l W-67 Revision 2 l

At the time this qualification program was completed, significant prac-ticality problems existed in completing full scale environuental and seismic type tests.

As a consequence, Westinghouse believed that a reliable qualification could be established by employing well established separate effects methods to address environmental parameters and analysis to address ceismic capability, after a test to confirm the natural fre-quency of a prototype motor.

The qualif3 ' tion program required in WCAP-8754 was completed on thermal-astic Epoxy insulation system test samples that are representative of the insulation systems contained i: these motor applications when supplied by Westinghouse. The bearings employed in these motor applications are selected according to the recommendations of the Anti-Fraction Bearing Manufacturers Association as stated in WCAP-8754.

The completed test program provides tne requisite assurance that the only material likely to be affected by radiation during the post-accident operating phase, i.e.,

the insulation system, will continue to perform within specification. This assurance is enhanced by the additional margin included in the qualification program (see footnote 7) and previous tests on similar insulation systema (WCAP-7829).

7.

Margin is included in this qualification program by:

- employing multiple samples (8) during radiation testing j

I 8

- employing a conservative radiation dose of [2 x 10 ]b,c,e Rads.

For 7

current qualification programs, Westinghouse specifies 2 x 10 Rads (Figure 6-8, WCAp 8587) for 1 year post-LOCA for the gamma dose in the center of the pipe carrying recirculated water from the sump.

Westinghouse further reduces this dose by a factor of 5 to allow for the motor being located outside the pipe boundary.

- addressing potential in-service aging mechanisms due to thermal steady state conditions and cycling, start-up cycles, moisture and r?diation.

d O

W-73

y e

I t

6 e

e

- ---- LOCATION PURCHASE MOOfL NUMeER OR PUILDING aP.402 MAL 09

[tN]#p4 MENT 10 080(#

g21 ffPE OF EQUIrafMT pasaJf aCTt*E JET 111gAJE pa) et'=1 y g *Tro, a(g101,t4RNvLej*MNT wit.ru mesmfgg sotst sTO. w1Dr eaNGE PVC0 22-3006 BB.

f t.410.4n.

Liga tem 1 TINS iga _(I*3tyc3 TEMPte ATUng DECTORS PCS LOCP 420.423.

430.433 TEMPS F$a9 FIGUEt 6.!-7 T(MP1 F IGUFt 3 3 PR[fSI FSAR FIGURE 4.1-3 retSS: FIGLTE 13 treavt t HOUDS 5reat: % e Ct7S TID: 4.73e? # ADS 11D: !*6 PACS SU0ML96LNCta HD Sut ttlGGIIIC E : N/A Was Ot.[ r;'Of0ftri SUB)

JECIED 10 ALL ltSTS IL StellS? Its flaE111I'J3 t*-a rmt.unr}

TfMPs fSae FIGUpt 6.2-5A T L f;P I F IC L'W E 13 FRESSt F SAS FIGURE 6.2-4 FRESSI FIGU#t 13 SPeait I h0VES

$reatt 9, NCURS 1!0 3 4.71*6 B ADS TIDr te6 pads SUOMERGINCtl NO SL'Dfit 9GINC E : N/A ba$ ONE F20701sFE SUB-JICTED TO ALL TESTS 3(

SER1tS? TES

,***WW r

' % ~M eMe Me 4 m.___

geoeee. w s geom we -

i

\\

l s

W f

e Ort #APILITT OffpABILIff ACCupACT Op etsr0Nst ACCUDACT 09 BE$rCH5t of e'If pfyiT S cit'w, v e & fj g if*t engewis Yfat et m ste&Ytn er>Alf ric Af f ree street Aarj PETwM TI*t WITHOUT FAILUCt1 IIME W11*C"JT F AILLet FUL L ACCUR ACT TOLERANCE:

FUL L ACCUBACT 70 Lies *ltti (fute&L 30 DatS f'037 LOCA 30 D ATS 4 LCC A (NV.1 e/ $X e/=$X TIME ST FULL ACCL9&CTI TIMt AT FULL ACCUGACTt str027 2.03 PTCO 8F70831 30 CATS rcST LOCA 30 Da tS (LOC A INV. )

MEth00f itSF GJALIFILO LTFt1 2-1/2 1t ARS AG14 TIML a 168 HOURS A;1NG TEMP 3 1:1 C i

on.*6 B32a l

Revision 2 1

+

1 l

i l'

.!a l

t I

\\

PLitCM a 5E

---

LOCATION ------

CR3t e MODEL NtrBle C#

SUILDING AB}CEM4L C9 (NV!9C45ENT TO y*

• tt TyFLE1?JIPfENT P a ssL* a q.[(?ie_ Jf tHf!FICaf f 0'4 P9 #0C*1 T A", Sa ++ g o acqrt*er (NVicN8'f NT m_f CM Wy f F f E')

10109 SitM NOUNTED NANCO EA-180 RS 7126.87018.

Cf4JC'_01H_N, S E4 Coritif Nr3 linty Sw!TCH 6 '02 A.6 34 7, 81494.B.C TEMP: F 5A9 81GURE 6.2- /

TELP: P!CLTE 17 LCV-463 FCE551 F5AR F10Upt 6.2 1 reg 55: Fgcu;E 16 LCV-451, Sriraf t 2 NOUliS

$f'2 A f 8 96 6tCURS 88F1.

T101 7.167 940$

TIDI 2.04

• 6 8A05 FCV44 6 StKME9GtHCEt Pe)

SLSt*t #GC HC ( ! N/A PCV4454 1.a5 071 FF0f 0f1FE SUD-PCv4458 JFCTED TO ALL TE5f 5 IN 5t d lF S ' vf 5 p'n_(Nin t i f ras 3 w e r # + +i t t ime*,

7 t ne* : graw piclof 6.2 5A t i t i' B li a* s it rSt*18 FSAO f tCI,wt 4. 2 4 184'.1: I D wi in St uav i 7 Mos**1 esati:

9,.

i i ter-

?!O: 7.166 Rac5 fin: 2.0. e o cans Suett(E 0[NC(l NO

$LPnf W.* ut t :

H, 4 Was Of.E ET0f 0firt Sun-JtC1(O 10 ALL f t)f 5 IN 5tal[5? YES

.-.... ~,.-

1

T

,b 1

CPf9ASILlff Cf!DASILIIT ACCT 9ACT CD R E S PCMS E ACCtM ACT CF B '5&45E

'f 2 '."l'fl P L"*'_*1' 4]Il I'"L.#lE!]'5 "T *il 3 TI"E I!

• d'd8IIS 7'lI'7dN 'I I

'Off 3F

'O t t 35 NCT APPL!C AF Lt pagi Apptgtag(t g g s:$ o g g

1. tPC9T !.D r NAMCO CtHTWOLS, sty, 1 PE THM 1 TEST GU ALIF!to LIFT: FOff 6 asths it.=t: OggMass A3tNG TEMP 2 200 F CR-$9 B39a l

Revision 2 1

i l

1 l

1 1

4 4