ML20205S259

Summary of 860326 Site Meeting W/Util,Dibenedetto Assoc,Inc, Sandia & Sargent & Lundy Re Status of Qualifications of 10CFR50.49 Cables & Maint Records History Review.Viewgraphs & Attendees List Encl

ML20205S259
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/10/1986
From:	Shemanski P Office of Nuclear Reactor Regulation
To:	Heitner K Office of Nuclear Reactor Regulation
Shared Package
ML20205S237	List: ML20205S234 ML20205S259
References
TAC-42527, NUDOCS 8606120128
Download: ML20205S259 (37)

Text

a 9

6uc4 rare E

{

[ \%,

g UNITED STATES NUCLEAR REGULATORY COMMISSION

j wAsmNGTON, D. C. 20555

%,...../ APP 1) 1996

Docket No. 50-267 MEMORANDUM FOR

Kenneth Heitner, Project Manager, Standardization and Special Projects Directorate, Division of PWR Licensing-B THRU: Olan Parr, Chief, Plant, Electrical, Instrumentation and obg Control Systems Branch, Division of PWR Licensing-B FROM: Paul Shemanski, Senior Electrical Engineer, Plant, Electrical, ,

Instrumentation and Control Systems Branch, Division of PWR Licensing-B

~

SUMMARY

OF MEETING WITH PUBLIC SERVICE COMPANY OF COLORADO (PSC) TO DISCUSS THE EQUIPMENT QUALIFICATION (EQ) PROGRAM AT r FORT ST. VRAIN, MARCH 26, 1986 j The purpose of this meeting was to discuss the status of the qualification of i 10 CFR 50.49 cables at Fort St. Vrain and the maintenance records history review.

Following the meeting, members of the NRC staff and a consultant from Sandia participated in a plant tour. Attendees at the meeting are listed in Enclosure 1.

Equipment Qualification Of Cables The program to qualify cables within the scope of 10 CFR 50.49 at FSV involves the identification of cable manufacturers / materials, physical inspection of cables, purchase order review, and a cable sampling program. The results are not conclusive for the identification of cable manufacturers / materials since there is no easy method to identify manufacturers / materials based on an exhaustive search of historical plant documents. The results of the physical l inspection of cables is not conclusive because cables installed during plant

construction do not have cable jacket markings. The purchase order review is not conclusive because not all cable manufacturers have been identified.

A summary of the PSC cable knowledge is, (1) all cable materials are known, (2) some cable manufacturers are known and, (3) there is no correlation between specific cable and manufacturer and materials for the majority of cables. PSC stated that if either the location or manufacturer of cable is unknown, it will perform a 100% sample in accordance with the cable sampling program.

The PSC approach to the resolution of the cable EQ issue involves, (1) qualifying cable materials, (2) using available industry knowledge, test reports, etc.,

for materials, (3) using historical data for manufacturing processes, etc.,

for materials and, (4) taking credit for less severe environmental challenges based on the Steam Line Rupture Detection and Isolation System.

Contact:

P. Shemanski X24607 8606120128 860601 PDR ADOCK 05000267 p PDRz .

9 APR 10 506 PSC states that it is not planning any additional cable testing and the method of qualification will be based on material analysis, previous steam line rupture testing, other manufacturer's IEEE testing, comparison of similar materials /

thickness and thermal lag analysis. The staff advised PCS that thef r method of qualification, particularly for- those cables with an unknown manufacturer, may not be acceptable. The staff pointed out that a cable traceability problem exists at FSV and recommended that PSC consider an option that would involve a cable test program to demonstrate compliance with 10 CFR 50.49.

PSC stated that a cable test program to demonstrate qualification would not be cost effective.' PSC agreed to provide the staff with preliminary copies of several cable EQ binders as soon as they are available. The staff will review the EQ binders and provide comments to FSV.

Enclosure 2 contains the viewgraphs on the FSV cable qualification program presented during the meeting.

Maintenance History Review

~

The maintenance history review involves the adequacy of maintenance records for certain equipment items and the potential impact on equipment oualification of those items. Enclosure 3 presents a summary of the FSV maintenance history review which involves a three phase effort. PSC stated that Phase 3 began March 26, 1986 and when completed, it will document the results of the Phase I and II reviews and will provide specific recommendations for each item that effects or potentially effects EQ. PSC and the staff agreed to hold further discussions on this problem area.

Paul Shemanski, Senior Electrical Engineer Plant, Electrical, Instrumentation and Conteel Systems Branch Division of PWR Licensing-B

Enclosures:

As Stated cc w/ enclosure:

H. Berkow G. Zech U. Potapovs

0. Lynch D. Norman, Region IV J. Bess, Region IV I

e ENCLOSURE 1 ATTENDEES AT MEETING NRC-PSC MARCH 26, 1986 Name Organization Paul Shemanski NRC/NRR Uldis Potapovs NRC/IE Jim Eggebroten FSV/ Tech Services Tim Prenger PSC-QA Services Mgr.

William Schwartz DiBenedetto Association, Inc.

Philip A. DeBenedetto DiBenedetto Association, Inc.

Bob Farell NRC/ SRI Michael Holmes PSC Nuclear Licensing. Manager Kathy Owens PSC-Licensir.g Bill Adams Sargent and Lundy Mike Spisak Sargent and Lundy -

Del Norman NRC/ Region IV Jackie Bess NRC/ Region IV James Grossman SNL Gary Zech NRC/IE Sam Marquez PSC Mike Niehoff PSC

i, .

ENcLoroRE 1 QUALIFICATION OF E0 SAFE SHUTDOWN CABLES AT FORT ST. VRAIN

• IDENTIFICATION OF CABLES

• ENVIRONMENTAL CHALLENGE,TO CABLES QUALIFICATION OF CABLE 3 i

i

___ _ __ _ _ _ _ . . _ - - . _ _ - _ _ _ . - _ _ _ _ . _ . _ _ . _ - . _ _ _ _ _ _ . _ . - __ _ _ _ . - - _ _ _ _ _ = .. -

4 I

i

.h i f i

I l

REQUIRED CABLES I

I

• IDENTIFIED CABLES SUPPORTING EQ SAFE SHUTOOWN SYSTEMS r

IDENTIFIED CABLES ROUTED THROUGH A HARSH ENVIRONMENT l i .

I i

I e

s t

4

1 I

IDENTIFICATION OF CABLE MANUFACTURER / MATERIALS NO EASY METHOD TO IDENTIFY MANUFACTURER / MATERIALS FROM CABLE NUMBERS EXHAUSTIVE SEARCH OF HISTORICAL PLANT DOCUMENTS RESULT: NOT CONCLUSIVE i

l

O i

PHYSICAL INSPECTION OF CABLES MOST RECENTLY INSTALLED CABLES HAVE JACKET MARKINGS

. TO IDENTIFY MANUFACTURER

~

<20% OF EQ SAFE SHUTDOWN CABLES CABLES INSTALLED DURING PLANT CONSTRUCTION 00 NOT HAVE JACKET MARKINGS RESULT: NOT CONCLUSIVE

'6

PURCHASE ORDER REVIEW REVIEWED ALL NUCLEAR (SAFETY-RELATED) CABLE PURCHASE ORDERS DEVELOPED LIST OF ALL PURCHASE ORDERS WHICH POTENTIALLY COULD HAVE SUPPLIED CABLE FOR EQ SAFE SHUTDOWN SYSTEMS

~

1 r

i

, .- - - - ---.--. ,.-,~.-- - - - , - - - -.r,.---

O RESULTS OF P.O. REVIEW MATERIALS FOR ALL PURCHASED CABLES IDENTIFIED NOT ALL MANUFACTURERS IDENTIFIED RESULT: NOT CONCLUSIVE ,

SUMMARY

OF CABLE KNOWLEDGE ALL CABLE MATERIALS KNOWN SOME CABLE MANUFACTURERS KNOWN -

NO CORRELATION BETWEEN SPECIFIC CABLE AND MANUFACTURER At:0 MATERIALS FOR MAJORITY OF CASES t

9O

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

CABLE SAMPLING PROGRAM MUST KNOW LOCATION OF CABLE OF UNKNOWN MANUFACTURER, OR PERFORM 100% SAMPLE 9

l l

l

SUt#4ARY OF INFORMATION ON CABLE OF UNKNOWN MANUFACTURER A ,

e &

E W # J M I E E

@ z W m E ,

8 0 E $ w i E a u

s t = o t M" x = 5 &

M a 5 5 E E M M W W

$ m 5  % e u 5 Y 0 B E E 1 PR 16 NYL PVC X X X 2 PR 16 NYL PVC X X X 2 12 BR NE0 2 12 XLPE PVC X * *

• X 3 12 BR NE0

• 3 12 XLPE PVC *

• X 5 12 XLPE PVC *

• X X 7 12 XLPE FVC X *

• 9 12 XLPE PVC * *

• X 3 10 BR NE0 X X X

• 3 8 BR NE0 X X 3 4/0 BR NE0 X 3 2/0 BR NEO X 2 250HCM BR NE0 X X X - Same # of Cond. & Size

• - Same # of Cond. & Size, &

Materials

i 1

RISK TO PLANT 1

SAMPLE / REPLACE ALL CABLE HAVING SAME SIZE AND NUMBER OF CONDUCTORS AS UNKNOWN CABLES

, DOES NOT APPLY TO CABLES WITH JACKET MARKINGS .

e 9

O s

, ,----,-n,-, , . _ , ------,,----------r- ,-, , r-----, ----,, ,-n--- .- -- --,

O APPROACH TO RESOLUTION QUALIFY CABLE MATERIALS

~

• USE AVAILABLE INDUSTRY KNOWLEDGE, TEST -

REPORTS, ETC. FOR MATERIALS USE HISTORICAL DATA FOR MANUFACTURING PROCESSES, ETC. FOR MATERIALS TAKE CREDIT FOR LESS SEVERE -

ENVIRONMENTAL CHALLENGE l

2

,.__,7 . 7 -- _.____. .___. _ . , _.,m, ,.. y, ,

ACCIDENT CONDITIONS COMPARISION OF ACCIDENT PROFILES THERMAL LAG

~

• RADIATION

• HUMIDITY

e

.i .

l i

.1 1

Comparison of Accident Profiles '

1

\ l'.

Comtdned SWR /PWR profue (typical) Q il 450 400

• 9 L,

i.

0 3

350l/

,00 ),

E .

1 7' F

! 250 i J

200 L

N I .

C

.4

'l k'

il i i i t il i

. t ggg I I I I 111 1 I I ii111 I i i f i ill 1 e i i iIll I e e e IIen ..

0.01 0.1 1.0 10.0 100.0 1000.0 10,000.0 ,

Time ener initiesten of accident (minutes) , '

(

(

- -5 I _

f e

8 ia  :

~

1

~

31 - _

! ,i -

d -

ub Y 2

=

7

a W

ll -

e*

1 C I b

1

[

y

\ -

= --

E 1

1 i /  :

=

e , / # _

C 7  :

• 2 i u N

%A

~

E 0

3 I  ! I 3 3 3 3 Q (J.) aangesedwel

l 0

l THERMAL LAG ANALYSIS USES METHODOLOGY OF NUREG-0588 APPENDIX B FOR SAFETY RELATED COMPONENT ANALYSIS WORST CASE PVC/PVC CABLE BASED ON CABLE GE0 METRY AND AMPACITY ,

CONSERVATIVE APPROACH ENSURES WORST CASE THERMAL LAG ENVELOPING TEMPERATURE PROFILE ENVELOPING HELB BLOWDOWN RATE JACKET WITH LEAST THERMAL RESISTANCE FOR T (JACKET) > T (INSULATION)

JACKET WITH HIGHEST THERMAL RESISTANCE FOR T (JACKET) < T (INSULATION)

FORCED CONVECTIVE HEAT TRANSFER COEFFICIENT FOR T (ENVIRONMENT) > T (JACKET)

NATURAL CONVECTIVE HEAT TRANSFER COEFFICIENT FOR T (JACKET) > T (ENVIRONMENT)

2  : d y _3 E  : If l 1 k

a f 9 a -

l t

a 1-j m

aj j

> 5 i g ~

o*

1 1

) _

g f 5 ~$

ll l /  :

I

.a

!! 1 5 $

1 t ,I e

r

[ .

E E -

a.

e . / -

c

= -

e m , *

! I s xl i

~

l ii '

%  % \q -

" i .

E E

S 8

2 n 8 n

2 8 2 8*

a n -

o -

Q (3.) eJnissedwal

RADIATION 400 RADS TID (i.e. MILD ENVIRONMENT)

NO SYNERGISTIC EFFECTS EXIST FOR FSV

HUMIDITY ASSUMED TO BE 100% RH FOR THE DURATION OF THE ACCIDENT

l .

CLASSIFICATION I CABLES

• MANUFACTURERS ARE KNOWN

• CABLE INSULATION AND JACKET MATERIALS ARE KNOWN

• MATERIAL THICKNESS IS KNOWN MANUFACTURERS IEEE 323 OR 383 TEST REPORT IS AVAILABLE

METHOD OF QUALIFICATION FOR CLASSIFICATI N I CABLES USE OF MANUFACTURERS IEEE 323 OR 383 TESTING

• THERMAL LAG ANALYSIS -

CLASSIFICATION II CABLES

• MANUFACTURERS ARE KNOWN

• CABLE INSULATION AND JACKET MATERIALS ARE KNOWN ,

• MATERIAL THICKNESS IS KNOWN MANUFACTURERS IEEE 323 OR 383 TESTING IS NOT KNOWN TO EXIST o

l l

METHOD OF QUALIFICATION FOR CLASSIFICATION II CABLES

• MATERIAL ANALYSIS SLAB TESTING (EQUIVALENT THICKNESS)

INDUSTRY ACCEPTED PUBLISHED INFORMATION

• STEAM LINE RUPTURE TESTING BASED ON MATERIAL CABLE CONFIGURATIONS

• OTHER MANUFACTURERS IEEE TESTING

• COMPARISON OF SIMILAR MATERIALS, EQUIVALENT THICKNESS, AND SAME CABLE RATINGS (I.E. 90'C, ETC. )

• THERMAL LAG ANALYSIS e

9 0 -

t-- - + - - - *- -- -- - , _ . , _ . _, , j _ _,

O CLASSIFICATION III CABLES

• MANUFACTURER IS UNKNOWN

• INSULATION AND JACKET MATERIAL IS KNOWN ,

• THICKNESS OF MATERIAL IS KNOWN J

• CABLES PURCHASED AND CERTIFIED TO IPCEA/ICEA STANDARDS l

l c

O METHOD OF QUALIFICATION FOR CLASSIFICATION III CABLES

• SAME AS CLASSIFICATION II

CABLES BY MATERIALS INSTALLED AT FORT ST. VRAIN Conservative Published Threshold Continuous Insulation Materials Operating Temperatures Reference for Temperatures Butyl Rubber 250*F Principles & Techniques of Radiation Hardening by N. J. Rudie, Page 11-5.

l Ethylene Propylene Rut;ber 266*F (302*F*) EPRI Materials Data Base -

(Okonite)* Several sources of same data Polyethylene 302*F EPRI Materials Data Base -

Several sources of same data Crosslinked Polyethylene 302*F Same as Polyethylene.

Silicon Rubber 392*F Belden Wire Catalog L-81, Page 11.

Polyvinyl Chloride 221*F Belden Wire Catalog 878, Rev. 1 Page 98.

I 4

i

• 0konite Report No. NQRN Materials aged 9150*C for 21 days.

l i

CABLES BY MATERIALS INSTALLED AT FORT ST. VRAIN .-

Conservative .

Published Threshold Continuous Jacket Materials Operating Temperatures Reference for Temperatures Hypalon (CPE) 275*F Dupont Elastomers Bulletin, 41875, p. 2.4.

Neoprene 250*F Principles & Techniques of Radiation Hardening by N. J. Rudie, page 11-4.

Several sources of same data.

Nylon 300*F Same as Neoprene, and Dupont design HBK-E-44971.

Polyvinyl Chloride 221*F Belden wire Catalog 878, Rev. 1, page 98.

Okolon (PE) 302*F* Okonite Report NQRN-1.

Okoprene 302*F* Okonite Report NQRN-1.

• Okonite Report No. NQRN-1 -

Materials aged 0 150*C for 21 days.

I l

ADDITIONAL TESTING TO SUPPORT QUALIFICATION OF CLASSIFICATION II AND III CABLES

• NUREG/CR-2763,' SAND 82-1071. JULY 1982

~

• SAND 82-1036A

• IEEE TRANSACTION ON POWER APPARATUS AND SYSTEMS

• HOW TIME AND HEAT AFFECT PROPERTIES OF PLASTIC

• PSC STEAM LINE RUPTURE TESTING l

l l

+

l .

I

NUREG/CR-2763. SAND 82-1071. JULY 1982 CABLESPURC$ASEDTOSAMEIPCEA/ICEASTANDARDSAS FSV CABLES

• CABLES HAD SAME MATERIALS AS FSV CABLES TESTED AT 145'C (293*F) FOR 96 HOURS .

• RESULT: NO SIGNIFICANT DEGRADATION AT FSV CONDITIONS

SAND 82-1036A

• EPR COMPOUNDS

.

• EFFECTS ON BOTH MECHANICAL AND ELECTRICAL PROPERTIES AGED AT 139'C (282*F) FOR 7 DAYS 4

• 2 RAMP LOCA TO 340'F

• RESULT: NO FAILURES 4

1 G

I

• -* * - - - - ,- - - - - - y, , , _ . . . . ..

g ,. _ _ _ _ , , __ _

s.

IEEE TRANSACTION ON POWER APPARATUS AND SYSTEMS BY R. B. BLODGETT AND P. G. FISHER. VOL. PAS 88 NO. 5, MAY 1969. " INSULATION AND JACKETS FOR CONTROL AND POWER CABLES IN THERMAL REACTOR NUCLEAR GENERATING STATIONS." -

• SAME MATERIALS AS FSV CABLES

• TESTS PERFORMED AT ELEVATED TEMPERATURES AND RADIATION LEVELS

• RESULT: NO MATERIAL FAILURES AT FSV CONDITIONS e

"HOW TIME AND HEAT AFFECT PROPERTIES OF PLASTIC", MACHINE DESIGN.

O MARCH 1975 PP. 79-81 BY J. E. THEBERGE, B. ARKLES, P. CLOUD.

• SAME MATERIALS USED IN CONSTRUCTION OF FSV CABLES

• DISCUSSES SHORT-TERM AND LONG-TERM EFFECTS OF ELEVATED -

TEMPERATURES

• MINIKJM OF 400*F FOR 100 HOURS

• RESULTS: SLIGHT OR NO DEGRADATION ON SEVERAL MATERIALS DUE TO SHORT-TERM EXPOSURE TO ELEVATED TEMPERATURE f

e imM

s.

l PSC STEAM LINE RUPTURE TESTING,

• REPRESENTATIVE SAMPLES OF FSV CABLES

• TESTED TO TEMPERATURES OF 650*F FOR 4 MINUTES

• RESULTS: SATISFACTORY i

1 a

me ,

,- , , ,- , ., ..--.-,-,,.---n----.- - - --- - -

ESTABLISHING QUALIFICATION FOR CLASSIFICATION I, II, AND III CABLES CLASSIFICATION I CABLES QUALIFIED - YES

• TECHNICAL JUSTIFICATION STCi CABLE CONFIGURATION AND MANUFACTURER TESTED TO IEEE 323 OR 383 (ACCEPTABLE TEST)

CLASSIFICATION II AND III CABLES QUALIFIED - YES

• TECHNICAL JUSTIFICATION

• SHORT-TERM ACCIDENT

• RADIATION 400 RADS-MILD ENVIRONMENT (N0 SYNERGISTIC EFFECT)

• STEAM LINE RUPTURE TESTING

• USE OF CONSERVATIVE THERMAL LAG ANALYSIS

• PUBLISHED DATA SUPPORTS SHORT-TERM EXCURSIONS AB0VE CONTINU0US OPERATING TEMPERATURES

• SUPPORTED BY OTHER CABLE MANUFACTURERS TESTING OF INSULATION AND JACKET MATERIAL e

8 8

g.

MAINTENANCE HISTORY REVIEW E N c to r u p. E 3

• ' 'O'4JECTIVE: To identify those items which are not identical to the asrprocured state.

SCOPE: Review of SSR/PTR's initiated prior to October 1,1985.

APPROACH: 3 Phase Approach ,

Phase I - SSR/PTR Bulk Review Develop SSR/PTR Master List (EQ MEL annotated to reflect components already being replaced or modified).

Perfonn Review in Reverse Chronological Order.

Compare component listed on SSR/PTR to SSR/PTR Master List.

Record Applicable SSR/PTR's and copy appropriate documents.

• Phase II - Determine EQ Impact Assemble SSR's/PTR's copied into System Packages.

~

Review & Categorize SSR's/PTR's copied as follows:

1. Work effects EQ l 2. Work potentially effects EQ

3. Work definitely does not effect EQ

• Phase III - Final Report Document results of Phases I & II Provide Specific Reconnendations for each item that effects or potentially effects EQ STATUS Phase I Review completed 3/19/86 Phase II in progress approximately 90% complete Phase III to begin 3/26/86 .

l

_