ML19254B013
| ML19254B013 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 03/28/1977 |
| From: | Schlosser R BURNS & ROE CO. |
| To: | |
| References | |
| PROB-770328, TM-0863, TM-863, NUDOCS 7909170675 | |
| Download: ML19254B013 (26) | |
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DOCUMENT NO:
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COPY MADE ON CF DOCUMENT PROVIDED BY METROPCLITAN EDISON CCMPANY.
Supervisor, Doct=ent Control, NRC
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S RADIOLOGl CAL REF ~*S 93 r
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Source for the Radiological Refere>>ce :
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THREE MILE T.SLAND UNIT NO. 2
,7 BUPNS & ROE INC.
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\\d FIELD QUESTICNNAIRE NO. ) 59 '?
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DATE
.%'i/->7 1.0 SYSTEM
<TbM,- /9fce, /ce.m Ir/e,"
hTX NO.
/23 2.0
REFERENCE:
2.1 Flcw Diagram or Engr. Dwg. No.
2cf2 fl ?
- <s 2 2.2 Elem. Wiring Diagram No.
2.3 R. O.
or Specification No.
2.4 Other 3.0 INQUIRY SCURCE:
General Ouestian Drawing Clarification R Test Result Equipment Clarification i
Test or Oper. Procedure Anticipated Problem L/
Immediate Action Required T 4.0 QUESTION Prcblem:
/h ea d* *J A 5'W s'r< o 7 20 9 2 s i 2, 6 ' 2,
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Name'
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.0 ANSWER: Vendar Dwg. Change Reg'd by UE&C Start yp Yes,
30 3
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.1 Date Cenpleted 3-23.??
B&R Engineer 0 A # vf
.2 Folic.,-Up Action req'd. cy S/ q. F'7 - o
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.3 Follcw-Up Action completed:
Date: c'-/A -J /
B & R Eng ine e:-Mb'W,.m JPIES:
E2W~
.W.
Heward,Jr.
R.U.
aensel D.
Lambert FCR
.J.
Toole G.P.
Miller S.
Kakarla D.T.
English
.E.
Wright J.G.
Herbein R.
Brownewell G.T.
Harper
.T.
Gunn Unit 32 Shift J.P.
Cady. (2)
.J.
Strcnberg Foreman W.R.
Ccbean m
e-3 u 'il OkJ J B&R Cog. Engr. r". cy/RD SSGk s
i
af's v MsM OF2 A N DUPil
- ~ 3s o 04y copies To:
BURNS and ROE, Inc.
DATE 7/3/79 l
WRCobean,Jr.
I ASDan MM To P. K.
De
/
/40$
FASpangenberg HRLane G.AL t
l MCrane FRoM R. P. Brownewell j gownewell Station Vent Stack Radiation Monitor, l
SUSlECT HP-R- 219 (TMI-II Recovery Program) s db spf hopf-LFerrante The B&R Site Engineering Grouc was requested by an NRC Representative
[3 (D.M. Collins-Radiation Specialis ts-5 chone: 717-782-3995/3996/3997) to 3
I o' ovide infornation en the subj ect i
EE r
A
' a dia tion M'
_. tor.
He requires any 5
55 R
b ack up da.u (history) for the accuracy E-2 G
of the is: kinetic sampling no le's cap-
!5 pj8 5s ability to provide a reprasentative si i
33 e+ g$5
!* P 5
sample of the discharge air in this particular ins tallation (i.e. single 3w. [
jj nestle in large duct).
- *1 b
's j 5
55 Also he needs any test data en velocity O2 tc traverses perfo: ned on the exhaus stack t
30 for accuracy deternination.e of the radi-b ation monitor.
Please research the in-
. < ~ ' ' ' '.
T; i
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)i jM for=ation and forward your findings to p"h
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PKDe
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Subjects W.O. 2555-02 Jor0ay Central Power and Light Company f, 3 Three Mile Island Nuclear Station Unit No. 2
~
Iso!:inotic No::les for At=cepheric Monitora g
/h /
Specification 2555-65 Referencus:
- 1) Enrns and Rce letter to Victorecn dated April 26,197S
- 2) Victoraen latter to Burns and Ree dated May 5, 1973 Auentest 7,1978 Mr. J. A. Mals victorecn Corporation M
M 1lF 9l 10101 Woodland Avence yg
y j1 9
C1cycland, Ohio 44104 Den: It. Mal::
With referencu tv cur lattar dated April 26, 1373, wo are revising the du== ficw rates. based on the actual field mea-sured ficv rates.
Tabulaud bulow sra the duct si;:es, old ficw rate and the final rsvised ficw rate of the at=ccpheric monittrs purchased um.lur the subjact order.
EcvLsnd Old nuct Duct 71cv Sample Flcw Ficw Ra'm Duct Size Rate in P_ro_bo Por Rate in SFCM in SCFM_
in Inc_hea CFM up-n-221A a.5 55,450 laa x 36 47,f00 HP-R-2213' S.5 56,450 GG X 50 47,500 HP-R-222A 8.5 13r725 33 X 30 10,885 IIP-R-2223 S.5 50,715 100 x 32 43,500 HP-R-222C S. 5 19,450 55 X 23 14,667 EP-R-222D 8.S 83,890 36 X 54 70,350 11P-R-22 8A 8.5 E3,390 92 X 42 70,1G5 11P-R-22GB 5.5 83,890 92 X 42 70,535
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Page 2 Victoreen Corporation Durns and Roe received your quotation for these prebes dated May 5, 3 378 as per reference (2) above.
.1 change notice will
}
be issued shortly.
We understand that the crice for the no -
- les would remain the same for 120 days ins'tead of the 90 days in your letter.
The Change Notice $12 dated June 5,1973 was ise-ued to P.O.
C-0102 in order to provide HP-R-220 (Automatic Samolina Unit).
Wo would appreciate if you could send us the appro'vn1 drawings tor HP-R-220 as early as possibic so that Field Change cculd i
be initiated.
~
Should you have any questions, please do not hesitate to cen-i g,
tact our Mr. P.
R.
De at (201) 265-9500, c.stension 323.
t <' O.f. 4 x '..'
3:c Very truly yours,
....h _
h a '.
A.
S.
Dam
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Project Managcr ASD/ PED /fap cc:
J.J. sarton, GPU R.C. Cutlar, GPU y]
R.J.
Tooln, CPU site j
klbl J. Brum=er, Met Ed Sita l
I e
COPIES TO:
BURNS and ROE, Inc.
DATE 7/6/79 WRCobean I
ASDam I
g FASpangenberg To vnewell
'RLane MCrane FROM P.
K. De JHagan SCGottilla SUBJECT W.O.
3475 GSadauskas Jersey Central Power and Light Co.
PKDe TMI Recovery of ( 2)
Station Vent Stack db Radiation Monitor
~
(HP-R-219)
REFERENCE:
Memo frcm R.P.Brownewell to P.K.De dated 7/3/79 In reference to your memo dated 7/3/79, I investigated the subject and fcund the following documents (enclosed):
1.
Telecon between M. Fitter (B&R) and D.
Smotzer (Victoreen) dated 4/2/73.
2.
Memo frca H.
Cady to S.C.Gottilla dated 1/15/75.
3.
Tech. Memo 6 68 dat_ed 3/18/75.
4.
Conference Notes dated 4/21/75 5.
Telecen frcm S.C.Gottilla to J.
Fennimore dated 4/12/73 with respect o GPU Problem Report PR #2699.
No changes have been made en HP-R-219 for PR #2699.
The reason for this was given en the last doc 1. ment (No. 5).
Regarding the last paragraph of ycur memo, I do not have any knowledge of any test data.
For vent stack test data, Met Ed and GPU startup should be contacted.
The ficw balancing of HVAC ccmponents were done and could be obtained frcm H.
Ycung (HVAC).
For your information, sample ficw centrol system for HP-R-219 is described on Victoreen's Cperating Instructions for Radiation Monitoring System (Pages 3-72 through 3-31).
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[,g BU :ZNS an d ROE, Inc.
o ATr.
1/15/75 WRCobean, Jr.
RJDobbs TO S.C.
Gottilla AWHagstrom SCMarathe FROM H. Cody FJBenner TSlock SUBJECT W.O.
2555-02 GHarper Jeraey Central Power and Light Company JEllwanger Three Mile Island Nuclear Station Unit 2 RWong Radiation Sampling Probe Location HCody EReed PGupta DHopson MDiLoren o KDuffy A review of the a:mospheric monitor probe pf (2) locations was undertaken by HVAC discipline db recently.
The approxima te probe loca tions are showr. on attached isemetric drawings No. AH-12, AH-13, AH-14, AH-15, AH-16 and AH-17.
The TMI-2 instrt.nentation discipline was requested to provide criteria for the location of these sampling prebes.
Upon review of the engineering criteria docu-ment, no such criteria ccuid be founc.
Further research into Regulatory Guide 1.21 pg. 1.21-2 shows tha t A. N. S. I.
N-13.1-1969 can be used for guidance.
This standard states on pg. 26 para. A 2 " Generally, the di :ance frem the' transition or elbcw to the point of sampling should be a minimum of five and preferably ten or =cre diame ters dcwns tream ".
Reviewing the isometric drawings against this requirement shows that this s-impra c ticalf if not impos s ible.
We therefore request you review the existing approximate prc' e locations and advise whether r
they are acceptable, and if you find they are not, edvise where they should be loca ted.
If required any special ficw conditioning should be indicated.
It should be noted that the ficw in the ducts is turbulent.
Please advise your disposition of the item as soon as pos s ible.
/I J'f j
H. Cody' HC/mc Attachment u, 1 h-
,H,
P. 6. F L
WRCobean TAHendr ick son SMcPherscn egoa*ti TECH. MEMO NO. 668 AhEagstrcm SCMarathe JWS tr ibling SRosen 3/18/75 HCody JFHagan SCGottilla TO:
R.
J.
Dobbs pf(2)
FROM:
S.C.Gottilla/J.Hagan db TM Book
SUBJECT:
W.O.
2555-C?
Jersey Central Pcwer and Light Company Three Mile Island Nuclear Station Unit No.2 NRC Regulatory Guide 1.21, Revision 1 Recommendatica Concerning Implementation
References:
- 1) Memcrandum, H. Ccdy to S.C. Gottilla, dated 1/15/75, on same subject
- 2) WPPSS Nuclear Project No.
2, Technical Memorandum No. 764, dated 1/28/75, en same subject (copy attached)
- 3) NRC Regulatory Guide 1.21, Revision 1, dated June 1974
- 4) ANSI Standard N13.1 - 1969 1.0 Purcase The purpose of tnis memorandum is tc present reccmmendations concerning implementationof Regulatory Guide 1.21, Revision 1, June 1974, " Measuring Evaluating, and Reporting Radioactivity in Liquid and Gasecus Effluents frcm Lighc-Water Cccled Nuclear Pcwer Plants".
2.0 Summarv Refe.ence (2) above is attached to provide a summary of, One basic r equ ir eme n ts of Regulatory Guide 1.21, Revision 1, and comments thereof as they apply to the WPPS No. 2 plant.
Most of the requirements cutlined in reference (2) are also applicable to
/
the Threu Mile Island Unit 2 Plant and may be so evaluated bv the Nuclear Regulatory Commissicn (NRC) at the t ime o f licensing.
It is, enerefore, impera t ive that any deviaticns from the require-ments of Regulatcry Guide 1.21, Revisicn i be identified at this time nd ccrrective action ins tituted accordingly.
1L;1
I Tech. Memo No. 668 Page 2 3/18/75 Reference (1) above has requested a review of the present sample point locations on TMI-2, and appropriate recommendations concerning compliance with the requirements of Reg. Guide 1.21 as it affects the collection and monitoring of representative effluent samples.
Of particular concern is the reference in Reg.
Guide 1.21 to the use of ANSI Standard N13.1-1969 "G u ide to Sampling Airborne Radioactive Materials in Nuclear Tacilities ".
A review of the TMI-2 design has indicated partial ccmpliance w ith the requirem:q s of Reg. Guide 1.21, Revision 1 (i.e.
for the liquid effluent.s. - See GPU Memo J.M.Vann to T.M.Cr immins, Jr.
of Oct. 18, 1974 and see also FSAR.) But it does not indicate ccmpliance with ANSI Standard N13.1-1969 (which is called cut in Reg. Guide 1.21, Rev. 1) in the ma t_er of probe sampling.
This memo will. therefore, concentrate en an evaluation of the present monitcring prebe design and location, and recommendations concerning implementation of 313.1, or practical alterna:es thereof.
It is to be noted that N13.1 is listed in :ne guide as an " acceptable standard for ceneral crincicles and cuidance for representative sample collection."
Of signtficence also in Reg. Guide 1.21, Revision 1 ts the use of such standards "to the extent cracticable".
It should be noted also that compliance with NL3.1 is a maior problem in almost all existing nuclear plants, and to cur kncwledge, _cractical alternate metacds of sampling have been implemented in place of N13.1 for all these plants.
3.0 Discussion 3.1 The ANSI tandard N13.1 - 1969, entitled "Gu ide to Sampling ALrbcrne Radicactive Materials in Nuclear Fac ilit ies " says, in 4.2.l.2, "To withdraw representatives samples from a duct or stack requires proper placement of a sufficient number of sample w ithdrawal points....and gu ides iccating sample removal pointu in ducts and stacks are given in Appendix A. The samolinc coint shoulc,,ce a mtntmum or- :tve crameters (or five times the maj cr d imens ion for rectangular ducts) dcwns tream from abrupt changes in ficw direction or prcminent transitions."
g\\s\\
1, h3
Tech. Memo No. 668 Page 4 3/1S/75 Suggested Number Duct Area of Points Less than 0.5 sq. ft.
l 1-2 sc. ft.
4 2-25 sq.ft.
6-12
> 25 sq. f t.
20 3.2 A review of the TMI-2 sam. ole probe locations indicates that virtually none of the.crches meet the r ec,u ir eme n t s of N13.1 with respect ~ to straight run lengths and number of sample withdrawal points.
This is not an unusual situation, as there does not appear to be any
- ether nuclear plant which fully meets the requir emen ts of N13.1.
To do so would invcive extensive rercuting of EVAC ducting involving straight lengths which are limited in most cases by tne confines of the building space cr mechanical in cer fer e nce s.
As a worst case, routing of ductwork cutside of bu'_lding confines, or the addition of building stack discharges, would also require considerat ion.
The consequence cf such frastic acti.vns are co ns idered abcVe and beyond the definition of "to the extent cracticable" and will not be addressed fur ther in tais T.emorandum.
3.3 The problem of multiple prche sampling versus single
.crche sampling aas been a subject of much discuss:cn on the WPPSS No. 2 project and, as of this date, has
- a. c t '~ e a_ n a_.# _# a_ _ ~ ' v a_ _l v _- a_ s v-i v e d.
's
- a_
y - a_ s a r..... _ a_ r. _
of the WEPSS Healta Physics Department to utilice s ingle
-crcbe sampling by calibrating the ductwcrk using tracer techniques, and locating the prebe at the mest recresentative sample location.
The acceptability of this t echn ique to NRC is still o.cen to c.uestion and will not be valif ated until operating data becomes available, e ither frca WPPSS or some other nuclear plant.
'T 7
-sLie
Tech. Memo No. 668 Page 3 3/18/75 Appendix A, Guides for Sampling frcm Ducts and Stacks, is not a part of N13.1 - 1969 but is included with :t for information purposes only.
It states, in part:
"In the region immediately d ~vns tream frcm bends or severe transitic s, ficw patterns may be markedly d is tor ted.
These locations should be avo id ed.
Some
.carticle segregation may occur according to site if particles are greater than abouve five microns, due_to inertial effects.
Secondly, establishing the correct sampling rate for isokinetic ficw,
(if required) at such positions may be dif ficult due to cross currents or other cr=#ar-ad motions of ficw set u.
b.y the
- ansition er bends.
Generally, the distance frca the trans ition or elbcu to the point of sampling snculd be a minimum of five and preferably ten or mere diameters dcwnstream.
In some cases this distance may be inadequate."
- and,
" Among the cr iter ia for a point or points from which a sample will be taken are:
The particle and gasecus ccmpest:ica is representative at the peint in the crocs secticn selected, or encuga points in the cross section are sampled essentially s imultane cus ly or sequentially to provide an average, representative sample."
- and,
" Square and rectangular ducts shculd be sampled frcm
.co in t s in tne crcss s ec t ion r e,t re s e n t inc. acproximatel ec.ua l area.
The number of sample withdrawal points snould be as follcus:
-7
- k. \\\\ \\".%
. 1 s
q n I-
Tac t.. Memo No. 668 Page 5 3/18/75 In the Cooper Nuclear dtation, a multiprobe sampie technique is being used utilizing so-called
" isokinetic manifold duct" assemblies (by Nuclear Measurements Corporation) containing up to 20 sample probes connected to a tw o (2) inch manifold oipe.
The probe assembly is inserted into the ductwork at the duct centerline, traversing the longest duct d ime n s io n.
In the case of multiple ducts, a probe assembly is inserted in each duct and the sample discharge manifolded prior to
. cn ito. ing.. In all cases, the probe assemblies were located so as to give maximu:a s tra ight run capability, although compliance with N13.1 could not be practically attained.
Exper ie nce to date at the Cooper Station has indicated little cr no problem wi th this methcd of sampling and that samples are consistent with anticipated results.
In additico, no adverse reaction from the NRC on the Cooper system has been observed at this time.
3.4 The placement of probes with regard to run is of concern because bends or transitions will cause distertions of ficw.ca t ter n, resulting in, for instance, la.ver inc. of heavy particles on the outside radius wall.
Stra.ght i
run is required so that hcmcgenecus dis tr ibution may reassert itself, and turbulent ficw (i.e.,
Reynolds' numbers in excess of 2100) helps th is.
In addition, a large' number of probe lccations in tne cross-section of the duct w " alp of fse t the effects of stratification on measurement.
A tabulation of the TMI-2 data shcwn in isome tr ic sketenes AH-12 through AH-17 toge ther with N13.1 requirements is shcwn in Attachment "A".
It is seen that only HP-R-2213 meets the min imum r e cu ir e-ment for upstream run, although HP-R-225 and 226 do not fall short by very uch. ' Note that th is min imum r e qu ir e-ment is the five diameters r e qu ir eme n t, wnile it is pointed cut in NL3.1 Appendix A that even 10 diame:ers
, may be an inadequa te d is tance.
.rurther, none of them
,a\\h
)b.
\\
i '
Tech. Memo No. 668 Page 6 3/18/75 has L
the recommended number of sample points. (It should be noted in tnis connection that e large number of samplinc..crobes oses des ign problems for isokinetic e
flew.)
4.0 conclusiens Eased on the above discussion and a review of the present TMI-2 sampling design, it is obvious that althougn the impl centation of ANSI N13.1 may be highly impractical at this t ime, some attempt will have to be made to assure the NRC that the TMI-2 plant has attempted to comply with the in
..t of Regulatory Guide 1.21, Revision 1.
- Also, a
or major constderation is On,e advanced destgn anc carr ica tion status cf the TMI-2 ductwerk, thereby precluding the practicality of any majcr duct redesign.
It is with these premises in mind that the follcwing recommendations are made for the TMI-2 plant:
a Relocate all affected prches in tne existing ductwcrk to cbtain a more fa"crable ficw pattern.
Marked-up copies of drawings AH-12 to AH-17 are available from S.C.Got t illa shcW ing new reccmmended locations.
Attachment "B " is a table shcwing new straignt run imorovemen ts resultinc. frcm such reltcaticn.
(Scme of the improvement shown is due, not to relocation of the probe, but to the assumpt ion that, since cur transition pieces are neither " abrupt" nor "pr cm ine n t ",
they can be considered as s tra ign run.)
Pro 4 ect s
personnel shculd also review cener possible duct run locations for alternate placements that will allcw for more compliance with the Reg. Guide.
b.
Obtain new probes similar to the design used on Ccoper Ye to minimice the effect of stratification in the ductwork.
The additional cost of such probes will be ccminal and will give added suppcrt to meeting the i n t e n_: of Regulatcry Guide i.21, Rev is ic a L.
Ecwever, sncuid TMI-2 30 d e s ir e,
A
\\
e N.
Tech. Memo No. 668 Page 7 3/18/75 itmav be.creferable to await fur ther operating data from Cooper or other plants before finalizing probe d e s ig n.
Should such be the case, it is expected that there will be no significant impac t on construction schedules at this time.
c.
Project personnel to initiate a thorough review of Reg. Guide 1.21, Revision 1 and WPPSS Technical Memo No. 764 to insure ccmpliance with remaining equirements of Reg. Guide 1.21, Rev.
1.
4 A w/
Prepared by
_//d! C a
(
S'C.Uottilla f
/ *
/
.w
/3. Hacan'
/
~
SCG/JH/ew n-.
I
)
! it !
ATTACIIM EtJT ' " A "
Dtict Sampling Probes LocaLion & tio. of ports (Present) 1,ongest Duct 11 0 of Dist. f"om Minimum Probe Sketch Duct Arqa Probe or transition Dist.
tio.
t io.
Dim. ft ft" Points (is)
(should be) is should be ft.
XLDD*
XLDD**
ft.
II P-It-2 20 All-12 4.5
'). O 1
8 8.8 2.0 5
22.5 Ile-It-221A AII-13 9.0 27.0 1
20 7.9 0.9 5
45.0 11 P-It-2 21 n All-14 S.S 22.9 1
10 54.5 9.9 5
27.5 II P-It - 2 2 S AJ-lS 3.9 10.2 1
8 18.0 4.6 5
19.5 226 AII-LS 3.9 10.2 1.
8 18.0 4.6 5
19.5 II P-il-2 2 2 A AII-16 3.2 7.9 1
7 3.5 1.1 S
16 8
-16 8.3 22.2 1
10 7.D 0.8 5
41.5 C
-16 4.6 10.7 1
8 12.0 2.6 5
23.0 IIP-It-22PA All-l7 7.7 26.8 1
20 9 to 18 1.2 to 2.3 5
38.5 B
All-17 7.7 26.8 1
20 9 to 14 1.2 to 1.8 5
38.5 XI.DD = Multiples o f the Longest Duct Dimension
- Minimum Requiremen t o f 1113.1 - 1969.
-4 P'
~
-d
ATTACHMENT "B"
Duct Sampling Probes Locations (Proposed Change)
Longest Probe Duct Dim.
Distance No.
(LDD)*
from bend ft.
ft.
XLDD**
HP-R-220 4.5 22.0 4.9 HP-R-221A 9.0 24.0 2.7 HP-R-221B 5.5 62.1 l'
3 HP-R-225 3.9 21.0 5.4 HP-R-226 3.9 21.0 5.4 HP-R-222A 3.2 4.5 1.4 HP-R-2223 8.3 7.0 0.3 HP-R-222C 4.6 12.0 2.6 HP-R-228A 7.7 18.0 2.3 HP-R-228B 7.7 14.0 1.8 Changing the straight run pcreicns to round duct will change the values in the table slightly, bpt will reduce the number of probes considerably.
- XLDD = Multiples of the LDD V\\\\
-i l 0. '
'
- 4, p '/ [
[.
cc:
THendrickson April 21,197 5 SMcPherson FPatti MAscher HReh CO c
- e.._rv..c e e
-.. O m. e.c.
v i
JStriblinc lMCody
'C3agcni S CGo ttilla
Subject:
W. O.
2808, 2962 NTolle Burns and Roe Nuclear Proj ects JZalavadia Review of Regulatory Guide 1.21 PPrincipe
" Measuring, Evaluating, and Reporting ACygleman Radioactivity in Solid Wastes and Re-SFox leases of Radioactive Materials in SEisenkraft Liquid and Gaseous Effluents from Fianghans Light-Wa ter Cooled Nuclear Power Plants "
JHagan P:
Date:
April 1, 1975 db Place:
Eurns and Roe, Inc.
Hempstead, New York
Purpose:
The purpose of'this meeti..g was to dis-cuss the present recuirements and trends in the nuclear industry with respect to compliance with the provisions of Regulatory Guida 1.21 Present:
Nuclear Measurements Corocration (NMC)
Larry Vaughn - Vice President Don DeMoss - International Marketing Manager Marlan Hildenbrand - Eastern Regional Manager Art Posner - Scientific Sales Corp.
Burns and Je, Inc. (3&R)
Frank Patti - Chief Nuclear Engineer Pat Princio.e - Proiect Engineer, Laguna Verde
- Mike Ascher - Project. tanager, Laguna Verde
- Norman Tolle - Supervising HVAC Engineer Jay Zalavadia - Lead HVAC Engineer, WPPSS Stan.rox - Supervising Ins trumen t E n g i n e e r, w.=.=.e 3
- Ken Langhans - Instrument Specialist Bernie Eisenkraf" - Instrument Engineer, WPPSS Jim Hagan - Sr. Supervising Ins trument Engineer R
G1n
\\1 /
e.o a_-
- v..;...e
(
Summary:
The meeting was called to discuss the various implications of Regulatory Guide 1.21, as it is presently being imple-mented and regulated in the nuclear pcwer industry.
NMC is one of the leading suppl _ers of equipment for such ap-2
-m_-
.g
__m
,_m--,-
-e 3
Conferer.ce Notes April 21,197 5 Nuclear Measurements Corporation Page 2 of 8 Rec.u la to rv. Guide 1.21 in a number of nuclear pcwer plants i.e.,
Millstone, Duane Arnold, Cooper, to ame a few.
Particular concern of Burns and Roe at this time is the ef fect of Regulatorv. Guid e 1.21 on the.cresent system de-signs for the WPPSS No. 2 and Three Mile Island No. 2 projects, which are in advanced construction and design stages.
etailed scussion:
1 Sample Probe Design a.
NMC indicated that their isokinetic manifold probe assemblies have thus rar been acceptable to the NRC and are presently installed at a number of plants including Millstone, Duane 3
Arnold, Cooper, and other similar plants.
They indicated that the only problem encountered to date has been at Mills:One No.
2, whereby the NRC recuired Millstone to change the sample probes from short side to long side sampling in rectangular ducts.
It is to be noted that at Millstone, the NRC did not insist en the straicht run rec.uirements of ANSI-N13.1, however, they did approve the multi-nan:le probe design of NMC.
The general feeling of NMC is that the NRC is becoming more and more concerned with compliance w'.th ANSI-N13.1, but has not fully enforced the "straigh:
run" requirements at this time.
b.
When asked about gettine a representative sample using the isckinetic manifold probe, NMC indicated that all probes e.re custom made and are designed to acccmodate the averac.e duct velocitv..
Thev indicated that the individual prebe openings on the manifold assembly are specially designed to give representative samc.linc. on an averac.e velocity basis.
c.
At Millstone and Cocper Nuclear Power Stations, multi-nc: le sample probes were designed with isokinetic ficw in the probe header with " estimated" ischine:ic ficw in the prche no::les.
The probe no les are inter-chanceable havinc. threaded ends.
This desie.n was ac-cepted by the NRC.
The prche is a single pipe (header) to which the neerles are attached.
Duane Arncid esec
^
n n\\
n/>
the " christmas tree" design with multi-nc::les spread t-f, cver the duct area.
NMC did not kncw if this (ANSI) 9 L' !
design was tested er proved ec yield more representative s3F0_inc.
4 6
Conference Notes April 21,197 5 Nuclear Measurements Corporation page 3 of 8 d.
NMC expressed an opinion that multi-probe sampling is going to bg a requirement and that single probe sampling is not going to be acceptable in future plants.
e.
Burns and Roe questioned NMC concerning the oossibility of individual samo.le orobes in air ducts which would be brought out to a common manifold assembly.
NMC did not recom-mend this.carticular method of sam.olin3 f.
Calibrated bvo. ass duct s am.= linc. technic.u es were also discussed with NMC, hcwever, NMC indicated that they are not aware of anY installations for this tv. o. e or o f any developments along this line.
Burns and Roe indicated that there may be some physical space problems associated also with this technique.
2.
Sample Line Routing a.
NMC indicated that they do not recc= mend long horizontal sample line runs to the detector assembly.
Vertical sample line runs are more acceptable.
Particulate settling and condensa-tion would be minimized with vertical runs th at are adequately heat traced.
Sample runs should be as short as reasonably practical.
b.
Burns and Roe inquired about the efficiency of sampling as related to sample line runs.
NMC indicated.that Carolina Pcwer and Light is presently doing line loss studies at the H.
B.
Robinson plant.
Preliminary information indicates losses for particulate ~ sampling to be in the order of 2%.
Results on iodine losses are no: available at this time.
NMC agreed to forward to Burns and Roe any further information on this study as it becomes availab le.
c.
The subject of iodine sampling was discussed with respect to line losses, plate-out, and sampling ef ficiency. NMC indicated that iodine is very sensitive to temperature and humidity, (N
with condensation and plate-out becoming a m
q problem in sample lines.
In addition, NMC D
1O indicated that ficw rate of the sample shcuid s
e, 4...4. ma., -
e,.r ; a 2,
2
..,.. _.. _s-...-..
v-s ow.
--v.-
~
Conference Notes April 21, 1975 Nuclear Measurements Corporation Page 4 of 8 e
of collection efficiency in the charcoal filters.
It was recommended also that iodine monitoring and sampling should be done as close to the duct tap as reasonably possible to maximize collection efficiency.
Plate-out, rimarily occurs at bends and in horizontal runs.
d.
NMC indicated also that the sample lines shou ld be fairly large, preferably one (1) inch, so as to provide for good sample ficw and collection.
3.
Monitoring Requirements a.
NMC indicated that it is their interpretation of Regulatory Guide 1.21 that two (2) chan:.als of continuous monitoring are required, nTmely noble gases and particulates.
Burns and Roe in-dicated that this differs with their interpretaticn of Regulatcry Guide 1.21 which requires continucus noble gas monitoring, and sampling of particula:es and
'cA'..e.
c a u...a
=.. - "we d.."4-'
=d
". a ". " - - -,
.n however, con:inue to watch for changes in interpreta:ica of Regulatory Guide 1.21 since both the WPPSS N0. 2 and TMI-2 plants are presently affected.
b.
Burns and Roe inquired on the effect of back-ground radiation en sample measurements.
NMC indicated that they have not fcund background radiation to be a problem in their monitors, pri-marily because of the lead shielding around the detector, and the use of beta sensi:1ve scintillation detectors which give a high yield-to-background ratio.
In addition, Nyc utilizes a multic?.annel measurement technique with background subtraction.
NMC discussed the monitoring requirements following c.
Thev. indicated that they have full in-hcuse seismic testing capability for con-tainment atmospheric monitors.
In addition, they are presently providing full sampl e conditioning for all conditions following a LCCA up to apprcxi-mately 62 psia and 340 F.
NMC also stated that
, g'{
they do not recccmend the use of the LOCA monitors
\\': u for leak detection inside of containmeit, but 1
recommend instead secarate q ',.
ic" level sensitivity monitors for such purpose.
They indicated that
Conference Notes April 21,197 5 Nuclear Measurements Corporation Page 5 of 8 the normal LCCA monitor would not be sensitive enough for effective leak detection.
NMC also indicated that they can provide containment hydrogen and oxygen monitors similarly qualified for LOCA service.
d.
With respect to liquid monitoring of effluents, NMC indicated that they prefer off-line monitoring instead of in-line liquid monitoring.
Reasons given were:
1) ease of shielding, 2) ease of calibration 3) and several times greater sensitivity of measurement.
Burns and Roe indicated problems of sedimentation associated with off-line monitoring, however, NMC indicated that provision is being incorporated in their systems to take this into account.
e.
NMC estimated costs for two (2) channel r.Onitor system (noble gas plus particulates) with fixed iodine sampling to be in the order of $25,000.
Seismic qualification to be approximately S4,000 additional.
f.
NMC indicated that in seismic testing thus far, they have had virtually no failures c - standard commercial instrumentat.on.
For example, recorders that have withstcod seitmic testing are:
1)
Honeywell Series 16 strip chart, 2)
L & N Model W, 3)
Esterline Argus Model ll24E, and 4)
Westronics Mll D q
The only failure they have encountered to date has (s'})
been with the L & N Mcdel M recorder.
/
\\.
(-
q qb' 4.
C;':nting Room Practice a.
Counting rocm locaticn and background radia: Lor
Conference Notes April 21,1975 Nuclear Measurements Corporation Page 6 of 6 effects were discussed.
Burns and Roe indicated that most counting rooms are located in the radwaste kuildings to avoid transporting of samples from building to building which results in greater health physics problems.
NMC indi-cated that they prefer a counting room back-ground of less than 0.1 mr/hr.
Burns and Roe indicated that the present plant designs call for backgrounds of less than 1.0 mr/hr.
b.
Burns and Roe questioned NMC on the requirements for RF shielding of the counting rcon.
NMC did not have any opinions on this item, however, they indicated that they would take a closer lock at this with respect to its effect on counting.
They indicated, hcwever, that their detectors and electronics are provided with built-in RF shielding.
c.
Burns and Roe inquired as to the availabil ty of data on recommended instrumenta:icn and equipment f-typical radicchemistry laboratories and counting rocms.
NMC indicated that they would look into this further.
5.
Miscellaneous a.
NMC indicated that they are presently in the local instrument rack manufacturing business and would like Burns and Roe to consider them "c r future projects.
Burns and Rce questioned NMC cn their contract capacity limitation,which was stated by NMC to be in the order of $250,000.
b.
NMC indicated also that they are offering seismic testing services on a commercial basis, shou ld Burns and Roe be so interest ed.
6.
Conclusions As a result of this meeting, it has become cbvicus thrt the NRC is taking a closer lcok at sampling techniques associated with Regulatory Guide 1.21, and that future plants will be coming under intensive s cru tiny.
s s
It also ac.cears that s inc_ ie c. o in: s a mo. l inc. orches n%
- not be accectable to the NRC and, as such, may may
)
i
Conference Notes April 21.197 5 Nuclear Measurements Corporation Page 7 cf 8 jeopardice licensing approval on future plants.
It is particularly important that Burns and Roe pursue this matter further so as to avoid licensing problems on the WPPSS No. 2 and'TMI-2 plants.
With respect to the extent of conti1u3us monitoring required by Regulatory Guide 1.21, tnere appears to be a diff erence of opinion between NMC and Burns and Roe whether single er dual channels of continuous monitoring are required.
Again, this item should be watched closely by Burns and Roe with particular at-tention being paid to the problems of backfitting should the NRC require two channels of monitoring in the future.
C-'mmitments, Agreements and Authorizations:
1.
Items Cwed by Surns a._d ' Roe None.
2.
Items Owed to Surns and Roe None.
3.
Additional Agreements.or Authorizations None.
Although the meeting was of an informal nature, with no specific centract or project involved, surns and Roe should take appropriate steps to follow up cn potential problem areas.
Specifically, these areas are as follows.
1.
Sample probe design 2.
Duct straight run design 3.
Single versus dual channel monitoring 4.
Sample line routing In addition to the above, Burns and Roe should follow 'to
,5)
Q('
f A V
Conference Notes April 2]
1975 Nuclear Measurements Corporation Page 8 of 8 on the line loss studies underway at Carolina Power and Light, with particular emphasis on iodine sampling.
Prepared by:
,*<MA (J. Magd.
Approval by :
,((Cofe V
JH:cf
Record of Tel mhone Conversation I I Y 'S To be confirmed Date Tee a.on 4 /I 2 W
( x) No To From Jos. Fennimore S.C.
Gottilla Name Name Company er Dept.
E40- TT
- Company or Ce
- t. "i"*^"aa" 7"c' n4u W.O.
2555 TO c t MT Uni" 37 Subject (s) Ciscussed oadiation vanitors -
D.o.
2600 Atmoscheric Samoline As follow up to earlier Conversation today between Fennimore Remass and P.K. De, Joe and I amplified the details of the discussion on the subject.
RM 4220 Joe said that the system supplied must be mcdified by the addition of autcmatic isokinetic flow tracking.
The presently-provided single sample rate is no longer satisfactory now that duct ficw is to be varied.
RM 4219 Since these have already been supplied with ficw tracking A&3 capability, thev. will automa-4-=v. ad";usu sample flow to suit the new ficw rate.
However, ;
mus" "r
eccg-nized that the sensitivity will go des by ratio of 108,000 (new flow) to 177,000 (old flow).
RM #'s (all the rest)
Since, in all of these cases, the new flows are lower, the sample rates m.ust be changes in order to maintain isokineticity.
The new rates were given to P.K.
De earlier today and are easily attained using the supplied bypass valve and ficw meter.
In these cases too, sensitivity will be reduced by the ra i:
of these sample rates.
censitivity:
. n a _, _, cases the sensitivity changes do not appear to be significant.
Hcwever, they are mentioned in Chapter 12 of the FSAR, and so must be changed there-in.
Shelly Morrison (SAR coordinator) will check with NRC to see if the changes are unacceptable.
If sensitivity must be brought back up to FSAR valae 2 methods are evallable.
The proper method is re-sizing of the sampling no::les.
This is no small matter and will require several months time (No: le are not stock items).
As a stcpgap measure, gear changes can be made to slow down the filter tape until such time as no: les are changed.
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H('(*u r d of Tolophone Conver i t. i o n
.PG9c 2 March 12, 1978 Mr. Fennimore says that Victoreen's hcme 0 3:4 (i
Clevelanc) has already concunicated *'hi s 452'ce I
incl. costs, to the client's field force.
'^
?.S.
.ilthot-g5 Mr. Fennimore is no longer recresent-ing he Rad. Mon. line for Victoreen, he wi'l7 be available #o
,--u-- consu.3 tation on this w o
..ooyem.
ye can c,e reached bv calling Vic o-se"n 'S
"-T m
C.evelanc, o c4-e, us4 g
_-oe 800 number and leav-w 4.
-ug a message.
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