ML18346A239
| ML18346A239 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 04/12/1978 |
| From: | Hoffman D Consumers Power Co |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18346A239 (11) | |
Text
consumers Power company General Offices: 212 West Michigan Avenue,.Jackson, Michigan 49201
- Area Code 517 788-0550 April 12, 1978 Director, Nuclear Reactor Regulation Att:
Mr Dennis L Ziemann, Chief Operating Reactors Branch No 2 US Uuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - REVISION TO ENVIRONMENTAL QUALIFICATION LETTER DATED FEBRUARY 24, 1978 a
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Consumers Power submitted a report by letter dated February 24, 1978 to address the Environmental Qualification of Safety-Related Equipment for the Palisades Plant.
The attached pages are a revision to that report and are the result of additional review of the February 24 report and plant modifications performed during the 1978 refueling outage.
Although Consumers Power remains convinced that all circuits that contained terminal blocks would operate as required in a post-accident environment, plant modifications were made at the request of the NRC staff.
These modifica-tions resulted in the replacement of four terminal blocks in the containment air cooler solenoid valve circuitry and one in the circuitry for Pressure Transmitter PT-0102D.
In response to NRC staff questions, the subject of hydrazine addition during a potential post-LOCA condition was reviewed with respect to chemical environ-ment qualifications.
Hydrazine at a low concentration (50 ppm) is not expected to add any additional impact due to its rapid decomposition and reaction with iodine.
Consumers Power responses to IE Bulletins 77-05 and 77-05A, dated December 8, 1977 and April 6, 1978, should be used as additional references to the environmental qualification of safety-related equipment.
7~::~ 1 \\)*~t)2C 17
2 These revisions complete Consumers Power Company's responses to the NRC letter dated December 23, l977.
David P Hoffman Assistant Nuclear Licensing Adl!l:i.nistrator CC:
JGKeppler, USNRC
ATTACHMENT Consumers Power Company April, 1978 Environmental Qualification of Safety-Related Equipment The following pages of our February 24, 1978 letter have been revised:
page 1 of 27 Rev. 1 (4-11-78) 7 of 27 9 of 27 13 of 27 14 of 27 25 of 27 page 2 of Footnotes II page 3 of Footnotes II
" (new)
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sv 0861 sws
~:ss sv 0062 sws sv 00611 SUS sv 0065 mm SV 0873 sws sv 0870 Sl/S sv 0867 sws sv 0869 sws J 350 sws J 355 Equipment List (EEQ) Section A FuncLlon Provide Cooling Water to Contain ment Cooler Re-circulating Fans Junction Box for Control Wiring to Scrv. Wtr.
CV's for Contain.
Air Coolers VHX-1 V11X"'.3*
Junction Box for Control Uiring to Service Water CV for Contain.
Air Cooler VHX-2 J,ocatton A1*en Sub Room c Yes 11
- 143
+ Yes
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t Yes
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t Yes
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+ Yes t
+ Yes
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+ Yes
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+ l'fes
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c No c
No Llml t.lug Env I ror;menti;.l Munufa.cturer"f Quo.ll fl cation Mbdel (*rvne \\
Cr Her la Autoniatic SW Environment Co No l LM-8316111
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Steel Box _,., - Environment W/Gasketed No 1 Hinged Cover
- W/Westing-house Style No. 8o5432 Terminal Block*
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Rev. 1 (4-11-78) r~nv:lrorunentnl llculgn ciuallflcaLion Pnlisntles 1 2'(
l'resuure 'l'empernture Humidity l'sio.
OF
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70 283° 100% fill
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120 340° 100% RH
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Rodi-atlon ChemicalH l.O l' Footr1ote 106 l
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- Footnote-2x107
- l Rads
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Sheet
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Metho1l o r (l11n I If 1 cation FSAR Pages 6-12F
.3.2(d)
Paragraph 6.1 Radiation Qua llfication by Valve
'ication for Similar Vendor Certi,f Refer to Footnote 3 and Ii.
Type Valve.
Box is Standar d Off-the-Shelf Item s are qualified for eport PEN-TR-77-83 Ter:r.inal Block Westinghouse R dated Sc:;iteinbe r 13, 1977 and trortheast Utilities Se rvice Company Report GEE-78-127 dat ed ~!arch 27, 1978.
radiation by engineering Westinghouse Research Qualified for evaluation at Laboratories.
- Same as J350 11 Ref Letter B 2/25/'{6 ECGS "Fail-Safe F Above.
ixel To Purple Date Analysis Discussing unction" e
I
Tog lio P'l' 0103 Rev. 1 (4-11-78)
LlmlLlnn l~n-~l ronmental Dcaign Qunllficntion Palisudm:;
J.ocation l~nvlronmcnts.l !----~*------.------r---..------1 Sheet ___ 7'----- of ___
2~7---*
---r---r---t Manufacturer/ QuaU fication Pren sure 'l'emperalure llumldit.y Rndl-Chemical::
McLhod of CtHaJlfi en ti on 1_Y_n_t_e_m1 ___ ru_n_c_t_l_o_n __
1Area Sub Room Hodel (Type)
Cdter:l.a raiu.
°F
'I.
atJonl------11------------*----
f!PS Pressurizer Wide-Runge Indicator c
Yes 142 Foxbo*ro Co Model *u611a11 Environment Mo 1 10 286° 100% RH
<lR/h J*'ootnote !Ref:
FSAR Pg 6-12c, Para 6.L3.2(c)
Over 1
40 Yr Test Model H611 - Added Ref Spe~ No 70P-010.
PS 0103 (PT 0103) Instrument Provides Indication Only; No Control Function.
Radia-tion Qu01lificution Data Derived by Purchuse Speci-fic01tion Re<1uirernent.
Refer to ~*ootnote 3.
PT-0104 installed during the 1978 refuleing outage hss a r1mge of 0-600 psig and provldes nn mlditionnl eource of pressure indication. Pr-0104 is n Rosemont model number 1152 preasure transmitter with design qualifications verified by Rose~~nt Qunlificution Test Report No 1171115.
Meet a Environm~nt No 1 requirements with the exception that redintion qualification is to 5xlo6n.
Toe
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.Jy1Jtcn LJmUlnn I f,oco.tlon l~ovironmcntr.i Function Manufacturer/ Quell ficatlon I
Area Sub Room Model (Tvne\\
Criteria SV 0507A MSS Close Main (Vent *rs. No R G Laurence Normal Sti:111n Isolation Model '1251134 Environment Valves CV 0510 &
No t
SV 0505A MSS Close Muin
'l'B No Steam Isolation Valves CV 0510 &
0501 SV 0505B MSS
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No sv 2113 L'l'C t
c No Automatic Sw Environment eve Operates Churgin Co Ho 2 Line Vulve WPx!NA 202-30l-2F sv 2115 L'l'C f
c No" Automatic Sw t
eve Operates Churgin,
Co Line Valve WPxlNA 202-301-21~
sv 2117 L'l'C eve f
c No Automatic Sw t
OperuLes Pres-Co surizer Spray llTX 8320A l6V Valve I
l!!nvJ.ronmcnl;o.l Dc:::Jen Quuliflcr..tion Pressure *rempcrature llumldity Radi-Chemicals P:ilo oil:
t£ otlon A IBIENT COi DITIONS NA NA t
t A ffiIENT cm DITIONS NA NA t
68 283 100 RH 2x107 Boric Acid + pll 5,5-6.5
- 68 283 100 Rll 2xl07 Doric lri.cid + pll 5,5-6.5 68 283 100 RIJ 0x107 boric kid + pll t>.5-6.5 Rev. 1 (4-11-78)
Pnllsmio:?fl Sheet 9
of 27 Method of Ct11nlifk nllo11 Reference Special Report Rev 3 Dated 6/30/75, Re Outside Main Steam Penet Room Redundent Set of SV sv-0508. 0510, 05111 and (Para 9.4.1)
As above except -
N6, located ration B to 05211 Redundant set of SVs to 0506, 0512 and 0513 (Par sv 0502.
a 9.li.1)
Ref purchase spec and c crt of 2li58Hl neeriug compliance ASCO form ilo date 4/13/76, ASCO Eugi Re11or~ 0112 date 6/11/76.
As !fbove.
Ref purchase spec and ce rt of 21158Rl neering
~orupliance ASCO form 1'10
~ate 3/15/76, ASCO Engi leport 0112 date 6/11/76.
./
Rev. 1 (4-11-78)
Llmltlnn Environment.al Dcmlg11 Qu11llfic11tlo11 Palisades Location
~nvironmcntr.i Sheet 13 of 27 lyGtein Function Manufacturer/ Quall ficat.ion Presoure Temperature Humidity Rndl-Chemlcalr.
Method of Q.n:illficnlJon Area Sub Room Model (TvTiel Criteria Psla OF otlon PT 0102A HPS Pressurizer c
Yee Foxooro Co Environment 70 286° 100% RH <lR/h Footnote FSAR Pg 6-l!il Press Safety M611-GM No 1 Over l
Para 6.l.3.2(c)
Injection & Re-110 Yr Radiatio'n Quuli ficution Data actor Scram Chan 1el Based on Purchase Specification P'l' 0102B
- c Yee Requirements.
Refer to Footnote f
3.
PT 0102C
- c Yee f
f PT 0102D
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c Yes J 521 340° 100% RH 2x:io7 Footnote Same as J350 Above-Page i.
!Junction Box for c No st*eel Box Environment 120 1
. Control Wiring W/Gasketed No 1 Rads for*Pl'-0102D
- Hinged Cover
.* W/westing-house Style
'lfo. 8o5432 Terminal
- Block
Tne t
Jyn en
_llit__
N 005 HPS N 006
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II 007
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N 008
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J 325L RPS J 329L RPS J 320R RPS J 324R RPS I
Function Power Range Flux Ch:iunels 1
Junction Box for Connecting Manufacturers Wire to Instru-ment Wire for N-005 For N-oo6 For N-007 For N-008 J,ocation Area Sub Doom c. Ho 1
No No
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No c
Yes c
Yes c
No c
No J.lmi I.Ing l~nv i ronmental Manufacturer/ Quali fl ca tlon Model (TYlle)
Criteria Gulf 'General Environment Atomi~ NP-6 No 1
- 1
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Steel Box Enviroruoont W/Gasketed No 1 Hinged Cover Refer to
- .Connect9rs Footnote 5.
. are Amphenol 74868-UG59-A-U
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i Imvlronment.al UcuJgn Qunllflcntlon Prl!soure 'fempernt.ure llumldity Ra<li-Chcmicalr.
Psla OF n t.lon Bo 300 l.00 RU yl05 NA R/11 nl on nv
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Rev. 1 (4-11-78)
Pnlisnden Sheet ll1 Of 27 Method of ~1allfJcnt ion 1Qualified per Neutron Flux Monitoring Spec No 2966-42 1-5-004.
- Refer to.Footnote 5.
Box and Connectors are st andard lification Refer to
- Off-the-Shelf Items.
Qua idata was not avialable*.
\\Fo~tnote 5.
Same as J325 L Above.
Same as J325 L Above.
' 'same as J325 L Above.
I'
[,Jmi tlng Cuble J.ocatlon l~nvl ronmcnt&l
- Manufacturer l Quall fl cation c~'.le lyat.em Function Area Sub Room Model {T:rne}
Cdteria XZ2 RPS P'r-0102A c
Yes Gener~l Elec Environment Company No 1 rr-0102n
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Yes
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PT-0102C
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Yeo Pr-Ol02D Yes i
Environment I62 American
. PCS Pr-0102D*
c No No l Insulated Wire Co.
,-~----.
~ev. 1 (4-11-78)
Environmenl;nl DcuJun Qunlifkntion Palistulcr.
Preaoure Temperol.ure llumldity Pola OF
'Ii 70 290 100
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75 340° loo%
Rodi-ation
~.5 x 07 lADS
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5x107 Rads Sheet 25 of 2*r Chemicals Method of Q11nllfJcotion Footnote F rsnklin Research Institute Lab eport No F-c2870, Sept 1970 1
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9.5 pH Borated Soluti~n IR Franklin Research Institute Reports #F-C 3463 & F-C 4197-1
. *A portion or the cable for l'r-0102D was not included in the original
, submittal
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aluminum the FSAR assumed no corrosion for hydrogen generation.
Some of these transmitters will become submerged at which time failure by seal leak.age and internal shorting would be competitive with corrosion.
PT-102.A through PT-l02D will have served their function prior to submergence.
PT-0751.A *- D and PT-0752 A -
D are required only for steam line and feed-line break events.
The effects of submergence on these pressure transformers is discussed in our March 23, 1977 submittal.
For the cables listed on the attached sheet the known exterior (jacket) materials are polyvinylchloride (PVC) and chlorosulfonated polyethylene (HyJ;ialon).
The jacket material for cable zcx is unknown; the material is not mentioned in the *Palisades cable description list or any known purchase specification. Far PVC and Hypalan the references mentioned earlier describe both materials as being resistant to dilute alkali and mineral acid solutions.
It is inferred from this that these materials would not undergo chemical attack by the sodium hydroxide and boric acid in the spray water.
The cable ZCX, for which the jacket material is unknown, is the coaxial cable far the power range safety channels N005 through N008.
It is not possible to offer an opinion on the chemical resistance of this cable.
However, again, the protection functions will have been completed prior ta initiation of containment sprays.
As mentioned earlier, the chemical resistances were obtained from standard references.
Unless a material was listed as being "resistant" or having "excellent resistance" to chemical attack by dilute boric acid or slightly alkaline solutions, it was assumed that failure due to corrosion would occur.
- 2.
The cable testing.was conducted at at least 49 psia which is less than the required 67 psia.
However, both temperature and relative humidity met design conditions.
Since the pertinent qualification criteria are temperature and humidity for cables, it is concluded that the qualification d~ta is accept-able.
- 3.
The radiation qualification data cited in these sections ~s the result of vendor contact or purchase specification requirements.
In no case is it evident that the equipment was actually tested to failure.
Thus, it is felt that in all these cases the radiation levels cited are the minimum levels with unspecified margin to failure.
Further, for the case of the pressure transmitters (with the exception of PT-103) the safety function is over within the first few minutes and, consequently, they would not be subject to the full LOCA doses.
- 4.
Due to lack of conclusive data relating to the environmental qualification
~radiation) of the ASCO valve model number LM-831614 replacement valves have been ordered and will be installed during the next appropriate outage a~er receipt of the new valves.
The failure mode of the existing valves (LM-831614) is identical to the failure mode of ASCO valve model number HT-8316A77 as noted in the Big Rock Point Plant (Docket No. 50-155)
Environmental Qualification submittal dated February 24, 1978 (ie. solenoid valve failure will result in the venting of the control valve and the valve will remain open).
2 Rev. 1 (4 78)
- 5. The nuclear instrument channels are included in the list since they provide a reactor trip function and are used in the accident analysis to terminate a variety of over power transients. A review of the currently effective accident analysis has shown that credit for over-power trip is taken in only one analyzed accident of the type that involves breach of a pressure boundry and the consequent adverse environment. For this incident (rod ejection) the trip occurs less than one second after breach of ~he pressure bound.ry and it is anticipated that at the time of actuation the environment at the location of the equipment would still be essentially the normal environment.
The nuclear instruments provide a backup trip for small break accidents, however, current analysis (CENFD-137P) takes credit only for the low pressurizer pressure trip. Although the time frame may be longer than one second these trips also occur relatively early in the incident (see for instance, top of page 131 of CENPD-137P).
3 Rev. 1 (4-11-78)