ML16341E335
| ML16341E335 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon |
| Issue date: | 07/13/1987 |
| From: | Trammell C Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8707160278 | |
| Download: ML16341E335 (16) | |
Text
r
\\
gag 0 8 f/'OCKET NOS:
50-275/323 LICENSEE:
FACILITY:
SUBJECT:
Pacific Gas and Electric Company (PGSE)
Diablo Canyon Nuclear Power Plant, Units I and 2
SUMMARY
OF MEETING HELD ON JUNE 3, 1987 REGARDING SUBMERGENCE QUALIFICATION OF MINCO RTDs On June 3, 1987, the NRC staff met with representatives of PGSE to discuss the submergence qualification of the MINCO resistance temperature detectors (RTDs) installed in the reactor vessel level indicating system (RVLIS) at Diablo Canyon.
A list of attendees is contained in Enclosure 1.
Handouts used are included in Enclosure 2.
The RVLIS at Diablo Canyon, provided by Westinghouse, employs MINCO RTDs for density compensation in the reference and variable leg impulse lines.
The electrical connection ends of four of these RTDs per unit (2 per channel) are subject to submergence inside containment under loss-of-coolant-accident (LOCA) conditions.
During equipment qualification (EQ) inspection (Report Nos.:
50-275/86033 and 50-323/86031) in December 1986, the NRC questioned the submergence qualification of these devices due to the lack of documentation of an actual submergence type test on the RTDs.
Records indicated that they are considered by PGSE to be qualified based on the testing in a LOCA chamber with analysis to support submergence qualification.
PGSE believed that the LOCA test was more severe than submergence, and calculations of static pressure showed that the LOCA test subjected the devices to a greater pressure than submergence.
The component parts of the RTDs that are considered potentially susceptible to degradation during submergence are the epoxy potted seal assembly and the Hypalon (CSPE)-jacketed, Ethylene Propylene Rubber (EPR) insulated "external" lead wires to which field run cable is spliced using heatshrink insulation sleeving.
The actual temperature elements and their mineral insulated "inter-nal" lead wires are encapsulated in stainless steel tubing with welded joints.
(Note that in other installations examined by NRC, the seals and external leads were above flood level.)
PGSE has developed more detailed information since the December inspection.
At this meeting, they provided documentation of EQ testing in which a Rosemount Model 353C electrical conduit seal assembly (ECSA), with a sealing system they contend is similar to that of the MINCO RTD, performed satisfactorily during a
2 week submergence test following LOCA testing (see enclosure 2).
PG5E also provided documentation of satisfactory LOCA/submergence testing of a different manufacturer's Hypalon/EPR wire which they contended is similar to the RTD external leads (done in conjunction with Raychem sleeving).
'vovsson's swords PDR ADQCN, 05000275 P
PDR Q
4 44 vr" I '>>4 4
I 4
4 4
4, 4
hv I'"I i>>1
't j
g I <<IIr 1
4 4,
4 p
I.<<
~ 4 4
>>4
)Itl ilt If I'.
>>I I ~
4)
If V
4 P
PII It I
II I
tl 4
II
~ VIII 4
II I 4 VH
. I.)V I
Iv II 4
II4').>> 'll
.Vl f*
,f >>)
4 I
t
~ I 4'4
=>>
r)IIL~ I ~
l I,
I II c
~~>>II 4 '
rf I
II' 4
Lf II t
4
"', )HI I II i))
>> I "l.>>H lf Iz"'>>. ll t P I
II,>> I>>
~ I V
4 r<>
4
~ IVVI )
V I
IP r
>>It<<<<It
~"I,Vr
.I...,
4
~
I ll 'il 4r fl 4
H 4
I '<<Ii) I t
44 4
I 4
H 4
4 I'>> v It fl-.
4 4
,I 4,4>>
I<<I 4
,Hf I
<> <<lI "'I I'
Hf tl ) 'Lg
~ 4
~
~ I If t
I I
I VII l,v<<r I 4
I "I
'I lt
'I
)" I!tI I 4 H
4 II 'I
- I 4
Ifl If Pk VIIIV
'4 )
)
4 HV 4
If
.I 4 I t
4 4/<<V VfV'4 II 4
I il 4
".'I, I"4, I, )
I 1 'I I a
~
~ Iv
PG&E stated that they have consistently held that the original qualification basis was adequate and that the additional information developed since December confirms their original determination.
Upon completion of the main PG&E presentation and discussion, we pointed out the possibility that we could still find the RTDs to be unqualified for submer-gence and hence the need to evaluate the safety significance of postulated RTD failure in terms of its impact on RYLIS operability.
Accordingly, various failure modes and effects were discussed based on the assumption that the RTDs, if in fact unqualified for submergence, would be expected to suffer some degra-dation when submerged due to moisture intrusion and creation of leakage paths.
Following this discussion, PG&E agreed to prepare a formal failure modes and effects analysis with which to assess the significance of RTD failure in the event they should be determined to be unqualified.
At the conclusion of the meeting, we stated that we needed to consider further the information presented before determining if the original qualification basis was adequate and, if not, whether RTD submergence qualification could now be established based on similarity to the submergence-tested ECSA and CSPE/EPR wire.
We also suggested that PG&E consider submergence testing of the RTD to confirm their analysis and PG&E agreed to consider it.
Enclosures:
1.
List of Attendees 2.
Handouts Original signed by Charles M
Trammell Charles M. trammell, Project Manager Project Directorate V
Division of Reactor Projects - III, IY, V & Special Projects DISTRIBUTION NRC
& Local PDRs PD5 Reading File GKnighton CTrammell OGC-Beth EJordan JPartlow H. Walker H. Mong
,U. Potapovs S. Alexander G. Schwenk ACRS
(
)
HBClay on (Region 1)
T. 0. )artin -
ED P D5 R 'RVIB ammell UPotapovs 6
/
7 r'f Q/$ /87 P
- PD5 Gg hton y7Iy /s7
>><<1 I <<lh a l fl h
l <<cl jih
~ ~<<ja 4 l<<
ir l >, hfij
- r<<b
<<)4 ha ~ ~ 4>>a r
I "0 1
~
)
4..)
i Ih)hl
~
I rI) ~i',I>>
I
)Dh
~I 4
Ij
'I gf, h,h
<<."0
>> )a')
<<)
,)c l,j 4<< l a.rj Ilil, j 2 j IV, rif
Sj<<
h>>h
~
l >>
ll all I il" ~
4 I)cia 4
c
" I I
f"'fi
',", I a ") <<cl Pri)j h
if I I<<
)JI ff'.y ill II<<I 4<<
th I
li'l )
<<r j r
h 4
~
<<4 I<<i h I'
lhl I
~,)
fj 4
a' j
j
.h rll
)
h
'I h
C 'if'4, l 4 Ih)ah
)<<Ii 'i.r ',* I 4
4.) I
- 4) 4 j
la<<
lf I ha)i
>>'a il
'I >>. Il ahl I
ff,i)<<II r
I<< I c.a i
)
a
~ )
I >>.4,'r<<r ) I 4 I I
'lf!Ji Q I II I I
)>><<<<)ir
')
4 a
I 4 j III I
ha I
f
~
fl a
ii hl a=liar>>r
<<j <<4 I if
<<I l j" ~
rhhr lf 1 jr<<
h 4
c, <<I
~ I,
) fill i I I
4 II) II)
)
'I
f f'g'I ii l', 1 <<)
I M I
I l I
ii,ll<<'
Ij )<>
I ital r I 4'
C I
il 4
I I
4 a
Hr. J.
D. Shiffer Pacific Gas and Electric Company Diablo Canyon CC:
Richard F. Locke, Esq.
Pacific Gas
& Electric Company Post Office Box 7442 San Francisco, California 94120 Janice E. Kerr, Esq.
California Public Utilities Commission 350 McAllister Street Sari Francisco, California 94102 Hs. Sandra A. Silver 660 Granite Creek Road Santa Cruz, California 95065 Hr.
W. C. Gangloff Westinghouse Electric Corporation P. 0. Box 355 Pittsburgh, Pennsylvania 15230 Managing Editor San Luis Obispo County Telegram Tribune 1321 Johnson Avenue P. 0.
Box 112 San Luis Obispo, California 93406 Mr. Leland H. Gustafson, Manager Federal Relations Pacific Gas and Electric Company 1726 M Street, N. W.
Washington, DC 20036-4502 Dian H. Grueneich, Esq.
Edwin F. Lowry, Esq.
Gr ueneich
& Lowry 380 Hayes Street Suite 4
San Francisco, California 94102 NRC Resident Inspector Diablo Canyon Nuclear Power Plant c/o U.S. Nuclear Regulatory Commission P. 0.
Box 369 Avila Beach, California 93424 Mr. Dick Blakenburg Editor & Co-Publisher South County Publishing Company P. 0.
Box 460 Arroyo Grande, California 93420 Bruce Norton, Esq.
c/o Richard F. Locke, Esq.
Pacific Gas and Electric Company Post Office Box 7442 San Francisco, California 94120 Dr. R. B. Ferguson Sierra Club - Santa Lucia Chapter Rocky Canyon Star Route Creston, California 93432 Chairman San Luis Obispo County Board of Supervisors Room 220 County Courthouse Annex San Luis Obispo, California 93401 Director Energy Facilities Siting Division Energy Resources Conservation and Development Commission 1516 9th Street Sacramento, California 95814 Hs. Jacquelyn Wheeler 2455 Leona Street San Luis Obispo, California 93400
Pacific Gas 5 Electric Company Diablo Canyon CC:
Ms. Laurie McDermott, Coordinator Consumers Organized for Defense of Environmental Safety 731 Pacific Street, Suite 42 San Luis Obispo, California 93401 Mr. Joseph 0. Ward, Chief Radiological chealth Branch State Department of Health Services 714 P Street. Office Building 88 Sacramento, California 95814
~ W Regional Administrator, Region V
U.S. Nuclear Regulatory Commission 1450 Maria Lane Suite 210 walnut Creek, California 94596 Ms. Nancy Culver 192 Luneta Street San Luis Obispo, California 93401 President California Public Utilities Commission California State Building 350 McAllister Street San Francisco, California 94102 Michael M. Strumwasser, Esq.
Special Assistant Attorney General State of California Department of Justice 3580 Milshire Boulevard, Room 800 Los Angeles, California 90010
LIST Of ATTENDEES Enclosure 1
JUNE 3, 1987 MEETING NRC C. Trammell H. Walker H.
Wong U. Potapovs S. Alexander G. Schwenk PGSE N. Tresler K. Herman C. Coffer B. Smith Bechtel R.
Oman
('
i ~
)
,C
~
MINGO RTD EP R/Hypalon Pigtail Braised Splice Ml Cable Conductors Stycast 2586 FT Epoxy Welded Stainless Steel Sheath Welded Glass Hermetic Seal Figure 1A ROSEMOUNT 353G Kapton Glass to Metal (Sandwich)
Feed thru Header Braised Connection Shrink Tube Stycast 2651 MM 1N" Epoxy Kapton Stycast 2651 MM 1N" Epoxy Figure 1B
~ ~
a 7
CLAIM TO FAME Basic Composition Mix Pre pa ration Mixed Viscosity centipoises CURE TEMPERATURE Curing Shrinkage Ioveroge) in/in CURED PROPERTIES Standord Color Isee Not~ I.)
Flexibility Hardness Shore Oorometer SPECIFIC GRAVITY YIELD STRENGTH pss Compressive, 0.2'/ otfset Elastic Modulus pn Compressive Impact Strength Irelotive/leod)
SERVICE TEMPERATURE
'f Iree Note 2.)
Thermal Conductivity bTU/hr.sq tl.'f/in Thermal Expansion in/in per 'f Water Absorption
% 24 hrs Dielectric Strength volts/mil'olume Resistivity ohm cm Dielectric
~
Dissipalion 60 c Constant Factor Iten b)
I Mc Relative Cost l~O>EI40J F17 359 c.
STYCAST 2651-MM LOW COST GOOD FLOW Filled Epoxies AddCot.9o 1
TYPICAL PROPERTIES 6000 R.T. or Elev.
.002 Black Rigid D-B9 1.55 15,500 0.7 x 10'.25 350'.2 22 x 10'.1 450 1 0ss 4.6 o 0.02 4.4
~ 0.01 3.7
~ 0.02 Very low H IH CC STYCAST 2850-FT HIGHEST THERMAL K LOW SHRINK Filled Epoxies Ad+ Catalyst 9,QP or 24-LV
'YPICAL PROPERTIES 70,000 R.T. or Elev.
.001 Black Rigid D.94 2.2 16,500 1.1 x 10'.3 390'0.7 14x10s 0.15 3BO 10ss 6.5
~ 0.02 6.3
~ 0.00B 5.9
~ 0.02
~
~
C
~gh hICI
~C 'p0 c
UNITED STATES CLEAR REGULATORY COMMISSIO WASHINGTON, O. C. 20555 July 9, 1987 50-275/323 Diablo Canyon Chief, Document Management
- Branch, TIDC Director, Division of Rules and Records, ADP REVIEW OF UTILITY EMERGENCY PLAN DOCUMENTATION MEMORANDUM FOR:
FROM:
SUBJECT:
The Division of determined that
Attachment:
As stated Rules and Records has reviewed. the attached document and has it may now be made publicly available.
Donnie H. Grimsley, Director Division of Rules and Records Office of Administration yC
'