ML20203J631

Package Consisting of Equipment Qualification Documents. Related Info Encl

ML20203J631
Person / Time
Site:	San Onofre
Issue date:	02/15/1985
From:	Carlisle B, Hover C, Root S SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML20203J617	List: IA-85-651, Further Response to FOIA Request for Qualification Rept for Incontainment Radiation & Ga Technologies Submittals Re Instrumentation.Apps B & C Documents Forwarded.App C Documents Partially Withheld (Ref FOIA Exemption 4) ML20203J611 ML20203J631 ML20203J646
References
FOIA-85-651 NUDOCS 8608050343
Download: ML20203J631 (42)

Text

,_

Songs Unit No.

233 pg

{

D CDM "M" No. _

M17609 Rev. No.

1 i

Date to CDM-Page I

_of 42 EQ DOCUMENT PACKAGE COVER SHEET Data File For Environmental Qualification of Electrical Equipment Considered important to Safety and Located in a Potentially Harsh rea EQUIPMENT NAME_

RADIATION MONITOR DETECTOR SPECIFICATION NUMBER _

5023-606-4 MANUFACTURER _

GENERAL ATOMIC COMPANY MODEL NUMBER _

RD-23 LOCATION INSIDE ALANT_ CONTAINMENT PURCHASE ORDER (optional)_

TAG NUMBERS UNIT 2 UNIT 3 2 RE 7820-1 2 RE 7820-2 3 RE 7820-1 RECEIVED CDM 3 RE 7820-2 MAR 121985 SITE FILE COPY

{

Prepared by _

C. R. HOVER...............<..#Date -

.y Reviewed by _

8. CARLISLE

[

,........................s, Date --

L-/Z +J' Reviewed by -

5. D. ROOT A

Date

& O-b 3

Approved by R. H. VERBECKb., 4dIf Date._._2 [: s e 5 M<

8608050343 860730 g j g,,,

go, f<

CDM "M" No.-

M37609 Rev.No._

l~

Page__. 7 INDEX OF REFERENCES 4C of _

FOR EQ DOCUMENT PACKAGE n

REPERENCE MUMSER REFERENCE 78TLE 1

Deleted DOCUME8t?80 MUMSER -

2.

~

Letter from F. 8. Marsh (BPC) to H. L. Richter (SCE) dated June BE-7099 22, 1983 (BechtelLogID) 3.

Bechtel Nuclear Calculation "120 Day Post-LOCA Dose Rate for Equipment N1140-13 Inside Containment" (BechtelCalcID) 4.

Design Specification for Plant Vent Stack High Range Radiation Gas Monitoring System 5023-606-4 (BechtelLogID) 5.

Final Safety Analysis Report, SONGS Units 2&3 6.

Coolant Accident (LOCA) Test on One Radi-W S023-606-4-46 ation Detector Probe Assembly Model (BechtelLogID)

No. RD-23 for General Atomic Company" dated October Reference 7) 10,1980 (Appendix 9 of

j a

7 General Atomic Company Test Report E-254-960 (Revised) " Test Report Class IE Design 5023-606-4-46 Qualification Testing of Analog High Range (Bechtel Log ID)

Radiation Monitor (RD-23, RP-2C, RP-23, and RP-20-01)" dated May 1,1981 8.

G eneral Atomic Report E-115-876 (Revised)

High' Range Gama Radiation Monitoring 5023-606-4-42 System Operation and Maintenance Manual" (Bechtel Log ID) dated June, 1981.

9.

Letter from Bechtel to GA Technologies dated March 3, 19831 of Attachment 6 provided as part BX-7379 (BechtelLogID) 10.

Letter from GA Technologies to Bechtel dated March 28, 1983; provided as HOTE:

ALL REFERENCES NOT INCLUDED AS ATTACHMENTS MAY BE RETRIEVED FROM COM I

h EE 30 40$ m3er g3pga

.i

COM "M" No. M37609 Revision No.

I Page 4

of 42 _[

ENVIRONMENTAL QUALIFICATION EVALUATION

SUMMARY

(THIS DOCUMENT HAS 11 ATTACHMENTS) i.

EQUIPMENT DESCRIPTION AND REQUIREMENTS RECEIVED CDhl "E"E"C" "o-

• • u A.

Component identification:

MAR 121985

1. Name RADIATION MONITOR

2. Spec. No. S023-606-4 Rev. O Date_10/10/79

3. Most Restrictive Location in Plant CONTAINMENT

4. Manufacturer GENERAL ATOMIC COMPANY

5. Manufacturer's Model No. RD-23

6. Manufacturer's Cat. No.

B.

Component used in POST-ACCIDENT MONITORINO System C.

System Function:

1. Reactor Cooling

2. Emergency Reactor Shutdown

3. Containment isolation 4.

Containment and Reactor Heat Removal-

5. Prevention of Significant Release of Radioactive Material to the Environment

6. Post-accident Monitoring X

D.

Component op-ation is:

Continuous X

Intermittent E.

Component must operate at:

DURING THE DBA AND FOR 120 DAYS POST-DBA (Indicate all "ON", "OFF", times for intermittent operations)

ON l

OFF t

l (Time measured with T=0 at initiation of DBA)

THIS

SUMMARY

IS BASED ON THE BECHTEL EVALUATION PROVIDED IN REFE R f

NCE .

s u..........,..

Page 1 of 10

COM "M" No. M37609 Revision No. _

l Page 5

og.

42 ENVIRONMENTAL QUALIFICATION EVALUATION

SUMMARY

REFERENCE l.

EQUIPMENT DESCRIPTION AND REQUIREMENTS (Cont'd.)

ao.

can.

F.

The component's normal environment is: SEE ATTACHMENT 3 Pressure O

psig Temperature 120

.p Radiation 1x10 rad (40 yr. total integrated dose)

Humidity 60 Other N/A G.

Limiting environmental condition fctiowing DBA is:

1.

LOCA profile X

Attached SEE ATTACHMENT 1

2. Other Time Periods 0 - 120 DAYS Pressure (psig)

SEE ATTACHMENT 1 Temperature ('F) _SEE ATTACHMENT 1 Radiation (rad) 1.4x108 g

g Humidit) (%)

100 Caustic Spra y

_SEE ATTACHMENT 1 (psig/ temp /ph)

Submergence NO (yes/no)

Other N/A H.

In service equipment mounting and orientation requirements:

1. No special requirements

2. Specialrequirggbgngigfgg9y00 MUST BE COVERED Requirement 11ITH HEAT SHRINK MATERIAL 7

3.2 11 Ref. GA TEST REPORT E-254-960(Rev)

II.

EQUIPMENT QUALIFICATION METHOD:

1.

Type Test X

(complete Section lii) 2.

Analysis or (complete Section IV) other methods

• POINT SPECIFIC DOSE FOR THIS EQUIPMENT; CALCULATION PROVIDED IN REFERENCE 3.

...... a. -..,..

Page 2 of 10

t 8

CDM "M" No. _ M37609 Revision No. - I

]

Page - 6

_ og _ 47 ENVIRONMENTAL QUALIFICATION EVALUATION lil. EQUIPMENT WAS QUALIFIED BY TYPE TESTS REFERENCE ao.

e4=.

cao=~

Yes X

No 6

(if yes, complete this section)

A.

Test Parameters:

1. Test profile attached-SEE ATTACHMENT _2

2. Other Time Periods

-O - 18 DAYS Pressure (psig)

_SEE ATTACHMENT 2 6

3.2 5

Temperature (*F) _SEE ATTACHMENT 2 Radiation (rad)

_N/A Humidity (%)

100 (SPRAY / STEAM ENVIRONMENT) 6 TBL.

16 Submergence

-N0 (yes/no)

III 0.28 MOLAR BORIC ACID (3000 ppm BORON) AND 0.064 MOLAR SODIUM THIOSULFATE BUFFERED WITH NaOH FOR A pH OF 10.5 FOR THE FIRST TWO HOURS, THEREAFTER DEMINERALIZED WATER WAS USED 6

TBL.

18 IV Caustic Spray (psig/ temp /ph)

Other 8.

The specimen tested was a representative of the component delivered:

Yes Y

__ No 6

1.0 1

Justification _ SONGS 2&3 EOUIPMENT ARE IDENTICAL TO TEST SPECIM MODEL C.

All tests were performed on same sample Yes X

No _

6 1.0 1

(if No, is justification adequate)

• Yes No Remarks 1 DETECTOR ASSEMBLY UNDERWENT TEST SEQUENCE O

CDM "M" No. M37609 Revision No.

I Page 7

of 47 ENVIRONMENTAL QUALIFICATION EVALUATION

SUMMARY

REFERENCE 111. EQUIPMENT WAS QUALIFIED BY TYPE TESTS (Cont'd.)

Ho-Paa-

• • • =

C'.. (Continued):

LOCA SIMULATION; POST-LOCA ENVIRONMENTAL EXPOSURE; SEISMIC SIMULATION. DETECTOR OUTPUT Define Test Sequence MONITORED THROUGHOUT LOCA SIMULATION AND 7

3.0 2

3.2 10 POST-LOCA ENVIRONMENTAL EXPOSURE SEQUENCES.

Was Test Sequence justified by vendor?

ye X

No 7

3.0 3

3.1 3,4 Justification COMPLIES WITH IEEE 323-1974. LOCA TEST PRIOR TO 10 1,2 1

SEISMIC WAS CONSIDERED A MORE SEVERE SEQUENCE. AGING NOT REQUIRE [.

D.

Margins applied during tests:

Pressure SEE ATTACHMENT 9

(% of required)

Temp.

SEE ATTACHMENT 9

(% of required)

Radiation

_N/A

(% of required)

Humidity 100

(% of required)

TEST CHEMICAL SPRAY COMPOSITION AND CONDITIONS Caustic Spray:

EXCEED SONGS 283 REQUIREMENTS. NO ADVERSE CORRO-SIVE EFFECTS NOTED.

p I

Temp.

(% of required) pH

(% of required)

Time

(% of required)

E.

Method of defining temperature of test specimen:

Direct Mounted Thermocouple INSIDE TEST CHAMBER 10 le 2

Heat Transfer Method Other (define)

F.

Radiation Sourde:

N/A se es ae = ese*a Page 4 of 10

COM "M"No. M37609 I

Revision No.

[

Page 8

of -- 42 ENVIRONMENTAL QUALIFICATION EVALUATION

SUMMARY

REFERENCE fil. EQUIPMENT WAS QUAllFIED BY TYPE TESTS (Cont'd.)

'^"-

G.

Heat aging method used: N/A Arrhenius Methodology Operating History Justify SEE ATTACHMENT 4 H.

Radiation aging method used: N/A - SEE ATTACHMENT 4 Radiation Source integrated Dosage 1.

Was review of materials susceptible to aging performed?

Yes X

No 7

3.1 3,4 10 1.2 1

(if Yes, identify materials) NONE IDENTIFIED J.

Temp / Press Transient Rate:

Time Temp Pressure From To

• F/Sec Psi /Sec SEE ATTACHMENT 2 (Describo all positive gradients)

K.

Was caustic spray applied at max temp and pressure?

{

Yes No X

6 TBL.

16, 2

III' I7' Flow Rate 1.0 GPM/FT t

IV 18 pH 10.5

• SPRAY COMMENCED 4 MINUTES INTO LOCA SEQUENCE WITH TEMPERATURE AT 318 F AND PRESSURE AT 77 PSIG.

l a*

• sse = = = e ue.

Page 5 of 10 L

CDM M" No. M17609 Revision No.

I Page-4 of __ 47 ENVIRONMENTAL QUALIFICATION EVALUATION

SUMMARY

REFERENCE fil. EQUIPMENT WAS QUALIFIED BY TYPE TESTS (Cont'd.)

'^"

L.

Were expected extremes of power supply voltage and frequency applied?

Yes Highest Lowest Voltage Frequency No X

Justify SEE ATTACHMENT 11 M.

Performance characteristics monitored:

Accuracy / Response Time N/A Continuously intermittently Method Repeatability N/A Continuously intermittently Method Operability SEE ATTACHMENT 8 Continuously intermittently Method _

N.

Describe qualification test interfaces:

CABl.E TO DETECTOR CONNECTOR COVERED BY Electrical Conna:tions HEAT SHRINK TtlBING 7

3.2 11 Piping Pneumatic Gas Hydraulic Mechanical Supports Other Did these simulate installation condition?

Yes X

No 1 1 1

1 (If No, justify) i

• ~

CDM M" No. _ M37609 Revision No.

I Page-10 og g ENVIRONMENTAL QUALIFICATION EVALUATION

SUMMARY

REFERENCE 111. EQUIPMENT WAS QUAllFIED BY TYPE TESTS (Cont'd.)

'^"-

"a's O.

Environmental qualification test report was issued by:

WYLE LABORATORIES i............

NORCO. CALIFORNIA 58522 10/10/80 e.......

i....i 5023-606-4-46 i....

P.

Was proprietary documentation included?

Yes X

No Not Applicable if, "No', proprietary documentation is available for audit at:

i................,

s.................,.s IV. EQUIPMENT WAS OUAllFIED BY ANALYSIS OR OTHER METHOD Yes No X

(if Yes, complete this section)

A.

Method of qualification was:

Analysis Operating Experience Combination On Going Qualification B.

Was completely assembled equipment analyzed?

Yes No C.

What components were type tested?

0

.'990.$ p.GPM

• • • ~

CDM "M" No. _H37609 Revision No. -

I

~

Page - Il

_ of _ 42 ]

ENVIRONMENTAL QUALIFICATION EVALUAT IV. EQUIPMENT WAS QUALIFIED BY ANALYSIS OR OTHE REFERENCE ont'd.)

L No.

• • a.

D.

Parameters of equipment / components analyzec:

• aQ Temp Radiation Press Humidity -

Cycling

_ Ccde applied -

Chemical -

E.

Methods of Analysis:

1. Temp. Arrhenius Method _

Time-

_ Temp-Source of Information Lit. Search Source-Other_

2. Radiation Data Scurce

3. Press Data Source _

4.

Humidity -

Data Source -

5. Cycling Data Source

6. Chemical -

Data Source F.

Margins applied:

Temp Radiation _-

Press Humidity Cycling Chemical G.

Were expected extremes of power supply voltage and frequency included in the analysis?

i Yes -

No _

(if No, Justify)

..... c:.. i..

puie a oe in

CDM "M"No. _ M37609 Revision No.

I Page 17 of _ 47 [

ENVIRONMENTAL QUALIFICATION EVALUATION

SUMMARY

REFERENCE IV. EQUIPMENT WAS QUALIFIED BY ANALYSIS OR OTHER METHOD (Cont'd.)

'^"

'a**

H.

If equipment was qualified by operating experience what parameters were applied?

Temp Radiation Press Humidity Cycling Chemical Sourceof Data Was environment equal to or morc severe than that required for equipment type testing?

Yes No 1.

Qualified life to be maintained by ongoing qualification program:

Yes No 1.

Is criteria for satisfactory operation defined?

Yes No

2. Is the periodic evaluation interval defined?

Yes No

3. Are the parameters to be evaluated defined?

Yes No

4. Are the components / modules to be evaluated identified?

Ya No Method of evaluation tests Parameter evaluation

5. Is vendor participation required?

Yes No Available, Yes No Describe participation I

~

CDM "M" No. _ M37609 Revision No.

I Page -

13 or 42 ]

ENVIRONMENTAL QUALIFICATION EVALUATION SUMMAR REFERENCE IV.

EQUIPMENT WAS QUAllFIED BY ANALYSIS OR OTHER METHOD (

'^"

'^ "l J..

Environmental qualification evaluation report was issued by:

i..............

i.................

i.....

i....:

i......

K.

Was proprietary documentation included?

Yes No Applicable -

If, "No", proprietary documentation is available for audit at:

i................

i.................

V.

CONCLUSION A.

Equipment Qualified to NRC Oualification Document _ NUREG-0588. CAT.2 B.

Equipment Qualified to Other Criteria _ IEEE 323-74t 344-75 7

1.

1 VI. RECOMMENDED DISPOSITION A.

Use as qualified for plant life of 40 yrs.

B.

Interim use for

_. years Justification-Vll. APPROVALS BY RESPONSIBLE OUTSIDE PARTY SEE REFERENCE 2 (When qualification is not performed by Edison personnel)

Prepared by Date Reviewed by Date p od W -

Date g,,,,,,,,,,,,,,,,,,,,,,,,

ee see e.e. este.

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i SOUTHERN CALIFORNIA EDISON SONGS UNIT NO.

2&3 SAN ONOFRE NUCLEAR GENERATING STATION CDM "N" NO.

M37609 ~

EQ CONDITION MONITORING INFORMATION SHEET REV. NO.

1

~

PAGE - 15 0F g 1.

Equipment Identification Condition

~

Replacement (seeSCE26-219)]

Monitoring

]

a.

Equipment Name:

Radiation Monitor Detector b.

Manufacturer:

General Atomic RD-23 c.

Model Number:

d.

Plant Tag Number:

RE 7820-1 ; RE 7820-2 2.

Age-Sensitive Materials Qualified Life NONE 3.

Replacement Requirements Material (s)/ Component (s)

Replacement Interval N/A 4

Condition Monitoring Require'ents All Installed Representative

~

m Devices Sample N/A - Condition Monitorino not reoutred for this item.

(See remarks) f

^

5.

Remarks No age-sensitive materials identified for this item.

Therefore, age degradation is not applicable for this program and Condition Monitoring would serve no useful function.

/

Responsible Nuclear Engineer

//t) /

f Signatpfe 'C.k' Hover Date PAX M F4 8

o Table 3.11-1 NORMAL, ACCIDENT AND DESIGN ENVIRONMENTAL CONDITIONS (Sheet 1) ft s

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Deserlettee lessed Boeust doet Seelen Bernal deet Bresga poemet deot besten mesual y

p Seelp Besuel doet Scot e Acet.

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Poet.

Post Accidset Ace,8-I Centstemoet *I 4

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320 300 3ee "I I

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to te les Ice Isle' 2.sels' 2.eelge 3,3,gge E4 (c)

(e) 2.9e80' (d) 3 ele *

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s therstes pie, at les ses les e

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ether volese are es tellene: Poet-sectM temperatores med presseres listed for the centelemmet are stest-tese s l a.

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o :o n 3 to 3e beers, pressere 3e Ib/te.'s, semperatore 23er o ese applicable to the stret 3 heers efter se seeldoet.

as fD C3 30 daye, pressere e Ib/te.8 Cettete selective egespusetle same coese, electrieel egelpmeet any he qualtf ted to the more cessereet8ee eel C, 13 0, temperatore 12er 4

emedattene are comeseteet eith the stee requirement for operentlety eed the egespso guettised to eestreemmeten esadialene lo y,

s mee speelflod to IEEE 323-8974.

-* 3 l

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mee are...t.ep-8,t-steidest spray cemettiene are e statore of berte seld med median hydroeide with a p 4.

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CDM "M" No. _M37609 Revision No.

1 Pa ge,_17_,_ of'43

\\

DESIGN ENVELOPE CURVE ACTUAL TEMPERATURE TRANSIENT FOR WORST CASE LOCA BASED ON:

A. 00USLE. ENDED SUCTION LINE SAEAK (SJ2 FT 3 2

8. 2 C00 LEAS,1 SPRAY C. CONTAINMENT NET FREE VOLUME = 2.30 x 10 FT3 I

j D. INITIAL CONTAINMENT TEMP = 120 F F

300 (i) j200,,.. '..-

'.,,,,... u..,,,,

iOO _

l I

t e

0 I

2 3

4 10 10 10 30 -

10 105 8

10 i

30 DAYS TIME, SECONDS l

d i

Updated l

Reference 5 SAN ONOFRE i

NUCLEAR GENERATING STATION I

Units 2 & 3 i

CONTAINMENT ATN0 SPHERE TEMPERATUkE V$. TIME i,

LOSS-OF-C001. ANT ACCIDEhT

,,__c,..,_

-~.,~====-etr='^--------------

^~

~

COM "M" No. _ N37609 Revision No. _

i Page 18 of 42 k

DESIGN ENVELOPE CURVE ACTUAL PRESSURE TRAN$ LENT FOR WORSE CASE LOCA BASED ON:

A. 00USLE-ENDED SUCTION LINE OREAK (9.42 FT ;

2 B. 2 C00LERS.1 SPRAY C. CONTAINMENT NET FREE VOLUME = 2.30 a 10 FT3 6

60 -

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Updated SAN ONOFRE h

Reference 5 NUCLEAR GENERATING STATION Unit: 2 6 3 CONTAINMENT ATN0 SPHERE l

i PRESSURE VS. TIME LOSS-OF-COOLANT ACCIDENT i

es e v-c_.

______,-_..--__,_.y

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

a CDM "M" No.

M37609 Revision No.

1 Page in of 4p During the injection mode, SONGS Units 2 and 3 chem.' cal spray is co Boric Acid (1720-2300 ppm Boron) buffered with Na0H for a pH of 9-10 at 85 F.

Minimum Emergency Core Cooling System (ECCS) flow requires an injection time of approximately 110 minutes; maximum ECCS flow requires an injection time of approximately 45 minutes. The pH is mairdained between 8 and 9 with a maximum Boron concentration of 2250 ppm during the recirculation mode. The containment temperature and pressure conditions during the spray system operation are as shown in Figures 3.11-1 and 3.11-2, and Table 3.11-1 of Reference 5, which are provided as part of this Attachment.

f

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CDM "M" No.

M37609 Revision No.

1 Page _ ?? _ of ap Reference 5, figures 3.11-1 and 3.11-2 provide the DBA and post-DBA temperature and pressure transient curves from the time of the DBA to 3 post-0BA.

Per Section I.E of Form SCE 26-324, the equipment must be evaluated against a 120 day post-DBA profile.

The temperature and pressure profile values shown on Figures 3.11-1 and 3.11-2 at 30 days post-08A are assumed to remain static from 30 to 120 days post-0BA.

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1

CDM "M" No.

M37609 Revision No.

1 Page 25 of 42 This equipment is inside the containment structure. As discussed in Section 3.11 of the FSAR (Reference 5), the inside containment normal and post-accident environmental parameters envelop all the outside containment areas; therefore, this equipment could be located in any plant area.

The containment parameter values listed on Attachment 1 are used in evaluating the level of environmental qualification for this equipment. Refer to for a tabulation of the appropriate environmental parameters for each area of SONGS 2 and 3.

l l

CDM "M" No.

M37609 Revision No.

1 Page 26 0F 42 The equipment item covered in this EQ Summary package is the RD-23 detector a ssembly.

Reference 7, paragraph 3.1, discusses the composition of the RD-23 detector assembly. As noted in Attachment 5, the Brand-Rex coaxial cable (which was used in lieu of the Rockbestos RSS-6-104 coaxial cable listed in Reference 7, paragraph 3.1), the Amphenol 82-816-1000 coaxial connector, and the Raychem WCSF heat shrink material are evaluated in separate EQ Summary packages. The remaining two components of the RD-23 detector assembly, the Reuter-Stokes RS-C3-1006-201 detector and the quartz cloth insulation, are inorganic and not subject to age-related degradation due to thermal or radiation effects.

Since none of the essential components in the RD-23 detector assembly are subject to either thermal or radiation age degradation, the test sample was not subjected to either a radiation exposure or thermal aging sequence in the test program.

The RD-23 detector assembly is required to operate for 120 days in an abnormal environment. However, it was tested for only 18 days in an abnormal environment.

The containment temperature and pressure LOCA profiles are adequately enveloped by the Reference 6 test profile (see Attachment 9). After 18 days, the post-DBA environment has essentially returned to normal conditiont.As a result, equipment operability dur,ing the 18 to 120 day post-DBA period would be affected by only thermal or radiation degradation. As previously noted, such degradation will not occur due to the materials of composition in the detector assembly.

l l

i i

CDM "M" No.

M37609 Revision No.

1 i

Page 27 0F 42 i

This EQ Summary package qualifies only the General Atomic RD-23 detector assembly. EQ Summary package M37621 qualifies the Raychem WCSF-N heat shrink material. EQ Summary package M37644 qualifics the Brand-Rex Coaxial cable. EQ Summary package M37707 qualifies the Amphenol 82-816-1000 connector.

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Attechment 6 CDM "M" No. _ M37609 Revision No.

1 0

Page pg of gp To E. Entaler

' * * - 3023-606-4 se San onofre Units 2 & 3

cei, March 10, 1983 Bechtel Job 10079 Action Itea #6249 h'"'

E. Richardson Environmental Qualification of Radiation Monitorina System W

Nuclear coewe se S. Freid A'

IAFD, 347E Est. 240 1

4. Lim J. Purucker E. Richardson

Attachment:

(1) General Atomic Radiation Monitoring System Spec. 606-4, Environmental i

Qualification (2) Letter F. 3. Marsh to Ted h11en (GA l

Technologies), dated 3/3/83, Los 31-7379 l

The following items are the response to Attachment (1):

1.

Amphenol connector 82-816-1000 tested in Wyle Test Report #58522 (5023-606-4-46) matches that listed in the ERRM operation &

Maintenance Manual (5023-606-4-42 pg. 6-8).

Connecton are covered by heatshrink tubing in both Units 2 and 3 asking visual verification tapossible. (See #4) 2.

Amphenol connector manufacturer's part #82-816-1000 (iten l

f50004261-00). Desc ription: Conn., plug, coax, str., 1.7 7 13, i

0.78D (502F606-4-42 pg. 6-8).

l 3 & 5. Letter dated 3/3/83 sent via telecopier to CA Technologies (attached) requesting required documentation and verification.

l Reply to be received by 3/18/83.

4.

Requirement for Raychem heatshrink tubing (VCSF-N) installation over Amphenol connector is required by ovg. 3023-606-4-0360-2062.

Telephone conversations with Mr. F.

at (SCE Startup), confirmed this heatshrink tubing was installe E. Rib ardson

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REFERENCE 11 LAD =GSGS (ST Ages AN DO 9 9/99

Attachment (1)

Page 1 of 1 CDM "M" No.

M37609 General Atomic Radiation Monitoring System Revision No.

1

- Spec. 606-4 Environmental Qualification Page 29__o f 42 1.

Verify that Asphenol connector installed in SONGS 2 and 3 is identical in all aspects to that which was tested in Wyle Test Report #58522 App. 9 of 5023-606-4-46-0, page 28.

2.

Identify Amphenol connector model number and type for itens 1 above.

3.

Provide the documentation for thermal and mechanical aging test data for this Amphenol connector and qualified life.

(See Ref. 5023-606 46-0, App. 4, page s 2-4.)

4.

Verify Raychem heatshrink tubing (WCSF-N) installed over Amphenol con-nection in SONGS 2 and 3.

5.

Define test sequence for Amphenol connector including LOCA test.

e a

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?

e REFERENCE 11

s

• 2nt (2)

Bechtel Power Corporation Engineers - Const u:ws 12400 Eas: pnoer.a Mgana, g

M" No.

M37609 ma. Ca sme 936M Revision No. 1 u

Nor

. c:4" l

March 3,1983 l

Iog RX-7379 l

GA h:h.%1cgies Post office Box 215')8 San Diego, CA 91130 Attention:

Mr. hd M_11en

Subject:

Southern California Rfison Q:rt.panf San Onofre Nuclear Generatirg Station, Units 2 & 3 Bechtel Job 20079

• phenol Connector E r.irarmental Saalification File: 9023-636-4-46-0

Reference:

(A) Dst Re;crt, Class IE, Design Qualification Dstirq of Ana'.cg R:.gh Ra ge Itadiation Ms.itor *

Dear Mr. Mt.11en:

In Reference ( A), an Mphenol con.wrtor, Ma$el 682-516-1000iN, is usuS to ser.:re a coaxial cable fra the rea$xt su>dule, RP-20, to the radiation detertor, RD-23. 'Ibe connector is in tarn caseeruf with a Raychem Ihatshrink

?.abing (WCSF-N) for p or.ection.

j i

Pollcwing a thortisgh examination of Deference (A), spcific docazmentatio.

with regard to the exact test seq.ance or proced.zre utilized in the the::aal arsi mettanical aging test and the IIG. test for the Mphenel c"mor ccm:1d. not be located. Certain references are un$e as to the agirg of con-ponents associated with the radiation detector,10-23; however, this does not prcride the sufficient doeurney.ation rws. aired for a class It itat sd.

as the Bigh Range, Radiation It>nitor.

Pierefore, the folicwing $dformatier. pertainirg to the abwe kphenol con-r%r is req.aestad to cat;slete Be:htel's erwirarmental galification docu-mentation:

a 1.

Define the test engance including the 14CA tast.

Provide the doosurntation for the thersal art! me$anical agirg tast 2.

If any test as not perfocusd, please 3rcwide justification for data.

t.he atission.

Identify the qualified life and the met.W used to detamine this.

I 3.

REFERENCE 9

- - - ~

Becntei rower corporaton Ms.rch 3, 1983

~

W CDM "M" No. M37609 Revision No. 1 Page 31 of 47 A prarpt response is great.ly ap;reciated. Thank you for your time ard effort.

Wry truly yours, BDCHT1", POWER CDRPOTan0K

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F. B. Marsh Project En;ineerirg stanaper los Angeles P:wer Division JM:kh cct Mr. E. L. Ric.6.ter, SCE 0

i l

r-REFERENCE i l

1 1

COM "M" No.

M37609 n...., q'..

Revision No. 1 Page 32 of _ 4p --

' GA Tschastes'st me.

ELECTS 0};IC SYSTEMS DIVISION liarch 28, 1933 sb;ddEciueoa<.r. sax m a 4.w Enchtel Pewat0erporation 12.00 E. Irperial Wy.

Fertialk, Ca.

93550 Attenti,n: Mr. F. B. Marsh sad,4e:t:

Ia:5cel letter Los Bx-7379 of 3 March 198J.

Des: l'.r. Marsh:

In reply to e.dject letter CA To:hnologies subcite the following:

1.

"F.e conne:ter fer RD23 consists of two parts. The dets.: tor ar.d of the ecnna:te-which uses a porcelain insulator, and catle end estir.g connector which uses a cross-linkad po1>-

icyre ie irsalater :tsoufactured by Amphenol (model 82-S16-103).

The desig. is such that eve, if the polystyrace insulator is11ad the matic; conne:ters porcelain insulator will maintain tre pr:per, center cenductor/ shield spacing and vill nongravent the za:1e.;: conca:tien fro i perfor=ing the safety function for the l

E013. Therefora, it is concluded that the A: spher.o1 connector has age re*.ated fail.re mechanis'a and no pre-aging to required l

n:

l pric: to he LOCA testiig. Thus, the test sequence for qualifying t

the RD23 was as described in E 254 960 (rev) and E 255 1061.

2.

W therral aging was required for the reason explait,ed in O).

also me: bad cal maing was net required, siece the connector is a permanant insta11stien and it has no requirement for disconnect during ite service lif e.

3.

The qualified life is 40 years with its maiatenan:e and replacement s:hedule as des: ribs.1 in E 254 960 (rev).

Very truly yocra, l

/

T. W Hallan Proj :t Manager 7.01:tk REFEREncg gn gQt/

- - - + =--

CDM "M" No.

M37609 Revision No.

1 Pa90 33

_ of _42 operability of the test sample was monitored by observing the live zero

~

current output of the detector. Although the current values were not given in either Reference 6 or Reference 7, paragraphs 3.2.1 and 3.2.4 of Reference 7 discuss the test results and state that the detector assembly performance was considered satisfactory.

Eight anomalies were reported in Notices of Deviation in Reference 6.

These anomalies involved failure of both the coaxial cable and connector assemblies which underwent the test sequence. Alterations were made to the test sample (a Raychem WCSF splice was applied to cover the coaxial cable connector) and the test sample assembly successfully passed the test. The SONGS 2 and 3 configuration is similar to that of the final test sample.

For an additional discussion of the test anomalies, see Reference 6, paragraph 3.2.2.

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CDM "M" No.

Revision No.- N37609 1

Page 34 of 42 As graphically shown in Attachment 1, the SONGS 2 and 3 temperature and pressure design curves provide some margin over the actual temperature and pressure transient curves for the worst case LOCA scenario.

On the following pages of this Attachment, the actual test curves (as described in Attachment 2) are superimposed on the design and actual transient curves for both the temperature and pressure parameters, in order to graphically demonstrate the available margin.

Note that while only one test DBA transient is plotted, in fact two test DBA transients were performed. The performance of the second transient provides an increased level of confidence for this equipment as only a single DBA transient is expected to occur in any accident scenario.

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70. Ts 3.E3

#,2cn cue:2,u cri:s a.ngust 19, 1981 gm 4

Bechtal Pcvar Corporation h

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12400 Estt Imperial H13 usy Norwalk, CA 90650 Attanticn: Mr. J. R. Puruchar Subj ect:

Scuthern Californis Edison Ccapany San Onofra Nuclear Gener' ting Statien, Units 2 & 3 Bechtel Jcb 10079

, ide R:nge Gas Mcnitor Radistics Dosa Post Accid 2=t W

File: S203-5 W bob 2eferenca:

1.

GA Doc =2ct, 2-254-030, "Tast 2 apert C1ssa I: 223ip Qualifiestics Tasting cf Ansic3 31 h 2:n3 a '- > ' e-' cn 3

Mcnitor (2D-23, 2?-2C, 22-23, =d 22-20-01)",

Dec=b er 15, 1980.

(

Attsch=ent: 1.

Bechtel Cc=ents en Refersnca 1, "?sch23a 20035 cc _..::t Sheats", 2 Shoots.

Daar Mr. Furucker:

Tha folicving ara GA reopensos to the setschad Bechtel cc=ents:

1.s) The first revisien to E-254-960 addressed radistien s3 :3 1

l f cr the individusi cespenents and asse= bliss.of th2 High

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2=32 1sdistics Mcaitcr.

Tha cal 7 cc=pcsact net l

in tha raport is tha asting cc= actor cf ths datacter. Tha cult asterial in tha cen= actor that is ncs-cats 111: is th2

' g g j!/!? FAT J.vi N u J Aissuistor. This is:sulater vill net 31 nific:ntl7 3

P3' @M#d@ ' ' dsgrada up to :n 1sts3 stad dcaa cf 10e reds.

I vgff OE)pqjn,-jy4 O 1.b) 7er redistics 23 23 322 1. s sb cv.n Raport 2-255-973 (2av.)

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• Attachment 10 CDM "M" No.

M37609 Revision No. I l

- 42 Page 38~

of 1

1 Page 2 August 19, 1981 j

sechtel Power Corporation j

1.c) The detector is designed to witheted temperatures up to 570'F.

It was tested to a peak temperature of 3550F per Appendix 1. Page 19 of E-254-960. The only point where this curve does not envelope the requirements of SacGS Units 2 ad 3 is fram 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to 30 days. This differ-ence is not considered,significat for two reasons:

1) the RD-23 is designed for a tanparature of 5700F and

2) the temperature transient is much more severe at the start of the IDCA the towards the end and once the de-tector reaches a steady state temperature, failure is unlikely.

1.d) When General Atmic Company was originally investigating and wire insulation aging, an activation energy of 1.2 eV was 1

1.f) chosen based on the best available information. This is in the range of values for wire insulators listed in EFRI Report NP-890-1 published in September,1980.

i.e) The chaber tenparature was measured using fast response i

thermoccupiss. These thermoccupids were installed within six inches of the test article.

If you have any questions, please contact me at (714) 455-4097.

I Sincerely,

}1 v %

eM S. G. Lewis Project Manager SCL/11a Att.

r-f PETEREg,L 32 19

1 1

e*

Attechnent 10 CDM "M" No.

M37609 Revision No.

1 Page 39 of _42 FACEhGE28035 CWHENT SHEETS 1) 5023-606-4-46 (E-254-960):

a)

Section 3.1 - Please justify why radiation aging is not required.

If radiation has been performed separately on its campament (in-cluding the emnector), please provide auditabla data.

b)

Radiation detector RD-23 test report does not provide adequate evidence that the in-containment components (i.e. detector, cable connectors, etc.) will function as required when placed in a radia-tion field. Vendor must demonstrate by test or other suitable me ms that the RD-23 detector can perform its required safety function for the required time in the worst case radiation environ-ment.

c)

The 18-day LOCA survival test profile run at Wyle does not envelope the SmCS 2 & 3 IACA profile. Please provide an analysis to just-ify that the difference between the two profiles is insignificat.

d)

Page 5 Table 3-1 and Appendix 4 Page 2-25 and Page 2-28 does.not adequately justify 1;he accelerated aging time and temperatures.

Specifically all accelerated aging of wire ad relays is at 1058C for 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />. There is no justification to relate this accelerated aging to different materials (i.e. activation energies) and quali-fied lines. For exmple, it is unreasonable to assume that hook up wire and relay magnet wire age at the same rate without proper justification. Please provide additional justification of acceler-ated aging time and temperatures and how they relate to a specific qualified life for each camponent.

e)

Ple'ase explain the type of sensor (e.g. thermocouple, did thermo-meter, etc.) used to define the temperature inside the test chaber during the LOCA test. Please describe the sensor location (e.g.

mounted on the test specimen, etc.)

f)

Flesse provide the basis for using the specific temperature and time during accelerated heat aging. An Arrhenius plot of cable insdlation material is acceptable.

l l

REFERENCE 12 6

0 1 CDM "M" No.

M37609 Revision No.

1 Page 40 0F 42 The GA RD-23 radiation monitor has its own power supply module which provides a constant power source. This power source is located in a mild environment. As such, testing the detector to extremes of voltage and frequency is not required.

Section 3.11.6 of Reference 5 discussed the effect of voltage and frequency fluctuations on EQ plant equipment.

That section is provided on the following pages of this Attachment.

i 9

l I

h

CDM "M" No. _ M37609 Revision No. 1

- 1 3.11.5.2.3.4 Normal Operational Dose. Doses due to normal operation over a 40-year plant life are considered. Contributions from piping con-taining radioactive material are included.

~

The results of the radiation calculations are shown in table 3.11-1 which presents the 0-120 day integrated accident doses as well as normal operat-ing doses.

3.11.6 VOLTAGE AND FREQUENCY FLUCTUATIONS 3.11.6.1 Voltare Sustained voltage variations at rated frequency specified for Class IE equipment operation are as follows:

4160 volts ac 110%

480 volts ac 110%

120 volts ac 110%

120 volt ac vital bus system 12%

125 volts de (range 105 - 140V de)

~

Voltage qualification is not required because electrical motors arc t

designed in accordance with NEMA Standard MG-1, which allows sustained fluctuations of 110% in supply voltage.

voltage dips to 75% of normal for 15 seconds. Motors can also function during Control devices are specified to withstand voltage deviations in accordance with NEMA Standard ICS.

All control components are within the applicable voltage ranges except for de relays.

During 125V de battery equalizing, the voltage is 140V de which exceeds the +10% (137.5V de) upper limit allowed by ICS.

Due to the small 2,5V de deviation and the fact that equalizing is done infrequently, operation or life of control devices will not be significantly affected.

For equipment powered by the vital buses, voltage variations are not a common mode concern. Each of the four protective channels are electri-cally isolated (IEEE Std. 279-1971) from each other and are separately powered by a similarly isolated vital bus, with each bus having its own inverter and battery.

These power sources are designed specifically to provide stable, regulated The four channel protection system is designed to protect the plant power.

with up to two of these four channels inoperative. In addition, the equip-i ment powered from the vital buses are designed for voltage variations of 110%, whereas the vital buses are designed to regulate voltage to within l

12%.

Therefore, voltage variations will not affect the ability of these systems te perform their required safety functions.

4)

Reference 5

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CDM "M" No.

M37609 1 Revision No.

1 Page 42 of 42

~

3.11.6.2 Frequency Frequency fluctuations which take place on the auxiliary power system are considered minor,and will not affect equipment qualification. Stability studies outlined in paragraph 8.2.2.1.2 indicate that.the loss of 1275 MW of generation in the western United States system will result in a fre-quency droop of only 0.1 Hz, and automatic load shedding to maintain fre-quency stability will begin at 59.1 Hz.

The diesel generator frequency is limited to 60 Hz 12% steady state and 55 Hz during transients. Vital bus power supply inverters are designed for 60 Hz 10.5 Hz output.

The frequency deviations described above will have only extremely limited consequences on the performance of induction motors and control components and have been specified to operate at 60 Hz 15 Hz.

For equipment powered by the vital buses, frequency variations are not a common mode concern for the same reasons as previously described in the discussion of voltage variations. The equipment is designed for frequency variations of 15%, whereas the vital buses are designed to regulate fre-t quency to within 10.5%.

Therefore, frequency variations will not affect the ability of these systems to perform their required safety funttions.

3.11.7 DUST Dust is not considered to be a degrading medium in the harsh environment areas at SONGS Units 2 and 3.

This is partially due to the seacoast loca-tion of the plant where blowing dust is normally not a major factor.

Additionally, ventilating units for the containment and auxiliary feedwater pump area are equipped with air filters. Good housekeeping practices within safety-related areas are also utilized to prevent large accumula-tions of dirt.

3.11.8 AGING Accelerated aging was not performed for all important-to-safety equipment which requires environmental qualification. For those devices, an aging analysis program was developed to evaluate the stresses imposed on the equipment which degrade performance.

The objective of the analysis was to determine a time period for which acceptable equipment performance is highly probable. The aging program consists of the application of one of the following methodologies.

One method is to examine the list of com-ponents of a piece of equipment, determine the components that are sus-ceptible to aging by either heat (thermal), or radiation (or in some cases by both heat and radiation), and then determine the qualified life for the most susceptible material. This method utilized Arrhenius techniques to determine the thermal aging period. This component then provides the limitieg qualified life of the equipment. The other method is the use of g

mechanical cycling which is applied to equipment subject to mechanical Reference 5 l

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GENERAL ATOMIC COMPANY ELEt.TRLillC S/T

.4 AfGARD

. s.. n FUNCTIONAL AND CNIRON ! ENTAL TEST'PEOCEDURC FOR SATCTY CllANNEL. ELE 30t.-3000

' :..J r7

- Reference Specifiestion ATP-156

!ssuc E Date 1-13-76 Page 8 of 33 N

'N.' 5 3.8 Environt-en tal CDM "t1" No.

M3761 Revision No.

0 1.

Co,nnect equipment as shown in Fig. 3.

Page 70 of 7C s

2.

Place drawer and preamplifier in environmental chamber with 500-ft 4

sir,nsi and test cables outside the chamber. Place test fixtute ELE 305-0000 with log calibrator and signal selector outside the

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chamber.

a 3.

Connect dual-pen strip dhart recorder to TE002, pin C for pen 1 i

and pin V for pen 2.

Set voltage range for 10 V full scale. Set E

time for 2 in./hr.

i E

-3 J

4.

Set currene sources to 1.3 x 10 A.

Place LOG CALIBRATE switch on test fixture ELE 305-0000 to position 6 (actually engraved g

position 7). Apply 115 V ac power to the drawer.

5.

Adjust remote gain potentiometer for +10.000 ::0.001 V de at E'

J13-V.

E 6.

Allow to varm up for at least 30 min. Measure and record voltage E

with LOC CALIBRATE svitch on test fixture ELE 305-0000 in posi-i

.. E tion 6 (actually engraved position 7).

Switch RATE CALIBRATE S'

switch on the drawer to CAL position to measure voltage at J13-C.

(

M Record. Return RATE CALIBRATE svitch te OPERATC position.

O Measure and record voltages at J13-N, J13-R, J13-T, and J13-V.

E Record ter.perature and humidity. Record voltages at J13-A, f

.5 J13-E, J13-J J13-L, J13-X, J13-a, and J13-c.

k 7.

Operate equipment at the conditions listed below and allov

'5 equipment to reach equilibrium. Repeat Step 6 for each condition.

Measure and record voltages.

s f

Time To Reach e

Ecuilibrium Draver Prea=olifier E

1 hr 10*C, 50: RH 10*C -WT

.2 1 hr 20*C, 50: RII 20*C, A ' 8' 1 hr 30*C, 50: RH 30* C '. 46 'F

_o_

I hr 45*C, 50: RII 45'C' :

I'8 4 hr 57'C, 50: RIl 57*C

-d~f

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I hr 57'C, 90% to 95: RH 57*C. *** '

1 hr Ambient

• 6 5

• C, 9 5 ~ RH '.* '

i 8.

Disconnect power and remove equipment from environmental cha=ber.

3.9 1000-hr Drife 1.

Conneet equipment as shovn,in Fig. 2.

Set current sources to l

1.3 : 10-3 A.

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• Res.ove drswe. from envire.msnesi chsaber during this test.

A REFERENCP 9 g'

Classification Acceptance Test D-28 A,y.oved

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