ML20207A686
| ML20207A686 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 09/11/1987 |
| From: | Donelan K, Poole C, Rothman K EPIDEMIOLOGY RESOURCES INC. (ERI) |
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| Shared Package | |
| ML20204J386 | List: |
| References | |
| FOIA-88-198 NUDOCS 8801290298 | |
| Download: ML20207A686 (41) | |
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- l LEUKEMIA INCIDENCE IN COMMUNITIES IN THE VICINITY OT THE 5 PILGRIM I NUCLEAR FOWER cENTRATING STATION 1
i i i Septe=ber 11, 1987 f i ( Sub=itted tot
' Boston Edison Co.
800 Scylston Street 3oston, MA 02199 i i
\ EPIDEMIOLOGY RESOURCES INCe i.
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1 i 4 LE!!KEMIA INCIDENCE IN CCMMLJNITIES IN THE VICINITY CP THE l 1 1 FILGRIM I NU0 TEAR PCWER GENERATING STATION i : i ! < 1 1 i 3 i j September 11. 1987 t .' l .l J Submitted tos 1 Boston Edison Co.
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800 Boylston Street Boston, MA 02199 }c ( .i l 1 l Prepared by: ;
. Charles Foole I Karen Donelan
)j Kenneth J. Rothman 3 Epidemiology fascurces Inc. 426 Boylston Street j Chestnut Hill MA 02167
- Telephone (617) 734-9100 1
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l l ; 1 i 1 ? i i I t TABLE OF CONTWrF5 ; 1 likt l l s umm a ry . . . . . . . . . . . . . . . . . . . . . . . . . . 1 ! I. Introduction ....................... 4 l l II. Materials and Methods . . . . . . . . . . . . . . . . . . . 5 III. Replication gf the MDFH Results . . . . . . . . . . . . . . 11 ! I IV. Cri tique o f th e IC FM Analy s e s . . . . . . . . . . . . . . . 13
, 7. Radiation Doses Fredicted from ltadicepidemiological Tables. 19 t
VI. Leukasta Rates in Relation to Presimity to Filgria I . .. 28 ' VII. References ........................ 36 , i t e l I i
5 LIST OF TABLES AND FIGmWS Pa,gg TABLES -
- 1. Comparison of 12PH and ERI Calculations of Observed and Expected Cases of Leukemia in the Five Coastal Towns Selected by the MDPH. by Sex. 1982-1984 ... .. . . .. 12
- 2. Observed and Expected Incidence of Acute Lymphocytic
, Leukemia Among Residents of the Five Towns Selected by the MDPH. by Age (0-19) and by Sex. 1992-1984 . . . . . .. 15
- 3. Observed and Expected Incidence of All Leukemias Except Chronic Lymphocytic Leukemia among Residents of the Five Towns Selected by the MDPH. by Age and Sex. 1982-1984 . .. 16
- 4. Observed and Expected Incidence of Leukemia Among Adult Residents (Age > 20 Years) of the Five Towns Selected by MD*JH by Leukemia Type and Sex. 1982-1984 . .... . .. 17
- 5. Rate Ratios (RR) Corresponding to Different Exposed
.- Proportions (Pe) in a Total Population (Exposed and Unexposed) with an Attributable Proportion (AP 7 ) of 37% . . 26
- 6. Directly Standardized Incidence Rate Ratics in Zones of Proximity to Pilgrim I, by Age and Leukemia Type.
1982-1984 . ... . . .. . . . . .. . . .... .. . 31
- 7. Crude Rate Ratios and Selected SMRs Comparing tones I and II with Zone III, by Age and Sex .. . . . .... .. 33 FIGURES
- 1. Twency-four Towns Identified by the MDPH as Lying k'ithin 20 Milea of Pilgrim I . ..... .. ..,. .. . 6 l 2 Towns in Tour Zones of Proximity to Pilgrim I . .. . ... 29 ,
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LEm3MIA INCIDENCE IN Col 0WWITIES IM M VICINTM OF '!1IE j PILGRIM I NUCLEAR POWER GElsMEATING STATION
SUMMARY
The Boston Edison Company asked Epidemiology Resources Inc. to review analyses by the Massachusetts Department of Public Health (HDPH) of leukemia incidence rates in com= unities in the vicinity of Boston Edison's Pilgrim I r nuclear pcver generating station. With data obtained frcm the Massachusetts , Cancer Registry, we were able to replicate the main results of the analyses the MDPH has conducted thus far. The observed numbers of cases correspond i exactly and the expected nu=bw s almont exactly between our analyses and those of the MDPH. l L We are critical of the way in which the MDPH has developed hypotheses about potential environ = ental exposure to ionizing radiation from Pilgrim I. The MDPh has concentrated on one highly speculative hypothesis about recirculating air above the coastline to the north of the f acility. Tho MDPH has provided no supporting data for this unusual hypothesis, despite the wailability of substantial amounts of meteorologic and radiation ) l nonitoring data. Neither has the MDPH contrasted the circulating-wind l hypothesis with alternatives, such as the simpler hypothesis that exposure is directly proportional to the proximity of one's residence to the f acility. l l l l l l
E.R.I. Page 2 Sept ember 11. 1987 t The MDPH analysis found elevated leukemia rates among adult males, but not among women or children. in five towns that lie along the coast to the north of Pligrim I. That the increased incidence rates are limited to adult males is inconsistent with explanations that might be proposed in , terms of general environmental exposures to ionizing radiation or other leukesogens. Adult males spend auch less time, on average. in the immediate vicinity of their homes in this particular geographic area than do women or 7 children. Consequently, adult males would receive the least amounts of such ! l exposures, on average, of the three groups of people, t ( We found lesser elevations of leukasia incidence rates in 13 towns { 4 that lie within 17 miles of Pilgrim I than the MDPH found in the five coaskal towns. Both our analyses and those of the HDFH yielded estimated 3 le tkemia incidence rate ratios that would be produced by high levels of radiation azposure, according to predictions from the Radicepidemiological ) Tables developed by the National Institutes of Health in 1985. Ihese l
- i predicted doses on the order of 1-100 rad per person, are much higher than j
l would be expected in the communities near PL1gris I or any other operating j nuclear power plant. The Radioepidemiological Tables were developed for the i purpose of estimating the probability that a cancer case was caused by 1 radiation arposure. The Tables are of ten used for lower doses and dose rates than those for which ef fects have been reliably estimated. Doses of
, 1-100 rad. however. f all within the range of observed doses in the studies that were used to coustruct the Tables (e.g., studies of survivors of atomic bomb blasts) . These were studies of comparatively high dose rates, but no 1
t E.R.I. Page 3 Sept ember 11. 1987 better data are currently available f rom which to estimate ef f ects reliably at lower dose rates. Thus, attribution of elevated leukemia rates to ionizing radiation released to the general environment by Pilgrim I would imply either extraordinarily high exposure that has evaded environmental monitoring or substantial conflict with the Radicepidemiological Tables. Of the accepted causes of leukemia, only occupational exposures to ionizing radiation or other leukemogens (e.g.. benzene) or medical exposures to ionizing radiation would be high enough to produce the increases in incidence among adult: that we and the MDPH have estimated for the towns near Pilgrim I. The case-control study under devalopment by the MDFH should emphasize a thorough essess=ent of the occupational history of each study subj ec' This assessment should .ocus on ionizing radiation f rom all so- eces and on industrial solvents, especially benzene, and should include a plan for validation and quantification of reported exposures by centseting emp16/ ers . l l l _ _ . _ _ _ - _ - - - _ _ .__ ._ - - _ . - _ _ -l
E.R.I. Page 4 Sept ember 11. 1987 1 I. INTRODUCTION The Boston Edison Company asked dpidemiology Resources Inc. (ERI) to revice analyses by the Massachusetts Department of Public Health (MDPH) of leukemia incidence rates in communities in the viciniry of Boston Edison's Pilgrim I nuclear power generating station.1 Boston Edison also asked ERI to conduct its own analyses.
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1 In Section II of this report, we describe tha data we obtained f rom the KDF3 and othe:: sources and the analytic methods we used. Section III presents the results of our successful ef forts to replicate the main MDPH res ulto. In Section IV. we offer a critique of the MDPH analyses, which are I based on an undocumented meteorologic theory. In Section V. we use r i Radicepidemiological Tables developed by the National Institutes of Health in 19852 to predict the average ionizing rsdiation dose that would produce the association reported by the MDFH for leukemias other than chronic lymphocytic leukemia. Section VI presents the results of our own analyses. which are based on proximity of residence to Pligria I. l l l l l
l l l l 1 1 E.R.I. Page 5 September 11. 1987 l II. MATERIALS AND MImlCDS i To replicate the analyses already conducted by the MDPH. and to conduct ; our own analyses, we obtained from the Massachusetts ,ancer Registry the l fo11cving data: I
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- 1) Listings by histology, race, sex and age group of all cases of
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hematopoietic and reticuleendothelial cancers reported in the years 1982, t' 1983, 1984 in the Commonwealth of Massachusetts. These cancers are assigned l code 169 in the International Classification of Diseases for Oncology ) (ICD-0). l
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- 2) Listings by hospital, date of diagnosis, sex, race, town, age, primary site, histology, and confir=atiota method of all cases with ICD-0 code 169 in
] ,. 24 Massschusetts towns in the vicinity of Pilgrim I (see Figure 1) for 1982 1983, 1984 To esti= ate the person-time in Maseachusetts and the 24 towns, we obtained 1980 census data 3 and projections made for 1985 by the State Data Center.' We used linear interpolation within categories of age, sex, race and town for the years between 1980 and 1985 to estimate the number of l
persons living in the state and in each town each year and thus the total l number of person-years for 1982-1984 I s l
E.R.I. Page 6 Saptc=ber 11, 1987 SOALt CF *Lis FIGURE 1 3 to 18 Twenty-four Towns Identified by the MDPH as Lying Within 20 Miles of .3. Pilgrin I ", C.,ye.g.a. TNI N Atl0N AL Su e vtY. Ch. , ,, ve, w . -.-
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E.R.I. Page 7 September 11. 1987 Data entry .r.d analysis posed various problems. The most significant 1 pt:blem concerned t1 # classification of cancers reported to the Massachusetts Cancer Registry. For the years in question, the histologies of cancers reported to the Registry were coded with three diff erent nosologic coding schemes: ICD-0 Systematized Nomenclature of Pathology (SNOP), and Healthstat. Although the SNOP and Healthstat codes are similar, there are substantial differences between these codes and ICD-0 codes, which are the standard used by the MDPH and the National Cancer Institute's Surreillance. Epidemiology, and End Results (SEER) Program. The MDPH had previously prepared a concordance among the coding schemes for leukemias; we obtained and used this concordance in our analyses after checking it for t consistency. We encountered other problems as we prepared the census data for entar. Census proj ections for 1985 were stratified by 5-year age group, gender and race (White Black. Other) . In all strata in which the number of people was i l l fewer than 10. the State Data Center did not report the number. Whenever we l could determine what the missing nu=ber was, we entered that number l otherwise, we arbitrarily entered the number 4. (Four was our estimate of the average number of unreported residents.) Census figures for 1980 were not stratified in the same race and age categories as the 1985 data. The Bureau of the Census reported race as White Black and Spanish origin. The category of Spanish origin included people who were also reported in White or Black classifications. People who were not White or Black were reported in the totals of the tables but
E. R. I . Page 8 September 11, 1987 otherwise were not represented. We entered figures in categories of White. Black and Other. classifying as "Other" all people who were not White or i Black and who were in the total. In towns where age groupings were not consistent with 1985 data, we distributed people proportionally according to their distribution in the state as a whole. i We wrote a computer program to read all data files and perform the calculations for the standardization of rates for individual towns and c certain groupings of towns. We determined the observed number of cases and person-years by age and sex in each town or group of towns for the following leukemia subgroupings: acute lymphocytic, chronic lymphocytic, other 1 ( lymphocytic, acute myelocytic, chronic myelocytic, other myelocytic, and all other leuka=ias. (3 To replicate the MDPH results, we combined these groupings into the f ollowing categories: leukemia, all subtypes (total leukemia. ICD-0 codes 1 9800 to 9940): leukemia, all subrypes except chronic lymphocytic leukasias (non-chronic-lymphocytic leukemias, ICD-0 codes 9800-9940 except 9823); and eyelecytic leukemias (acute, chronic and other combined. ICD-0 codes 9860 to 1 9866). It should be noted that these categories are not mutually exclusive:
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l the second is a subset of the first and the third is a subset of the second. j l In our analyses, we focused on the following leukemia categories: , 1 acute lymphocytic leukemia among persons age 0 - 19: chronic, acute and i other eyelocytic leukemias among adults and other non-chronie-lymphocytic j 1 leukemias among adults. For adults, we also used a broad category employed 1 i l
- , _ . _ . _ _ - - _ _ _ _ _ __ - -_ ___ - _ _ _ _ _ _l
E.R.I. Page 9 Sept ember 11. 1987 by the MDPH: all non-chronic-lymphocytic leukemias. Of the leukemias that occur primarily among adults. chronic eyelocytic leukemia has received particular attention in the literature on ionizing radiation and leukemia.2.5 Acute lymphocytic leukasia, which has also been linked to radiation exposure, is the predominant type of leukemia among children. We did not include chronic lymphocytic leukemia because of its consistent lack of association with ionizing radiation in the studies of higher exposures. Like the MDPH. we stratified the data for adult leukemias by gender it:suse of expected differences in exposure between men and women. Men are expected to receive a greater share of the ef fect of many occupational exposures and vocen are expected to receive a greater share of the effect of domiciliary environmental exposures. Unlike the MDPH ve also stratified by age. There were two reasons. First. the dif f erences in exposure between nales and f emaios apply only to adults; children do not receive occupational exposures and boys and girls would receive an equal degree of environmental exposure. Second, as noted above, the specific leukemia types are highly related to age. In contrast with the MDPH analyses, we did not compare a specific town or group of towns with Massachusetts as a whole, since the figures for Massachusetts would include the data for that town or group of towns. Instead, for comparisan, we computed rates in the remainder of Massachusetts by taking the total number of cases and the total number of person years in the Commonwealth within each category of sex, race (Black.
l 1 E. R. I. Page 10 September 11., 1987 White, other) and age (five-year categories) and subtracting free this total the corresponding number for the specific town or group of towns of I interest. l l l l l
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E.R.I. Page 11 Sept ember 11, 1987 III. REFLICATION OF THE MDPH RESULTS 1 In Tables 4a - 4d of the MDFM's report of March 16, 19871 , data are presented on the observed and expected incidence of cancers of the hematopoietic and reticuloendethelial system, with a specific focus on incidence of leukemias. We attempted to replicate the calculations of the observed and expected numbers of cases of leukemia in the five coastal towns of Plymouth, Kingston. Duxbury. Marshfield and Scituate during the years 1982-1984 (see Table 1) . The observed numbers of cases of all leukemias, all non-chronic-lymphocytic leukemias, and all myelocytic leukemias in the data available to us were identical to the figures reported in the March 16th report. ( Our calculations of the expected numbers of cases in some categories diff ered slightly f rom those of the MDPH. One reason for the difference may
- be that our expected numbers are based on the rates observed in the remainder of Massachusetts, whereas the arpected numbers determined by the KDPH are based on rates for the entire State, including the town or towns involved in the comparison. A second reason may be that we had to make minor approximations for those f ew numbers that were not reported in the town census figures. I l
We calculated incidence rate ratios standardized to the age-race j distribution of the population whose incidence rate was the numerator of l l each ratio. Rate ratios that are standardized in this way are kneun as ' SMRs.0 Each SMR may be considered the ratio of observed to expected l I
E. R. I. Page 12 Sept ember 11. 1987
- t. umbers of incident cases. SMRs determined from data reported by the MDPH and f rom our own calculations are shown in Table 1. The dif f erences between our results and those of the KDPH are trivial.
TABLE 1 Comparison of MDPH and ElLI Calculations of Observed and Expected Cases of Leukemia in the Five Coastal Towns Selected by the MDFB. by Sez. 1982-1984 CB SERVED ZIPECTED g HDPH ERI MDPH EKI HDPH ERI Leuke=ia-all subtypes: Males 22 22 12.1 12.7 1.82 1.73 Fem ale s 12 12 9.3 9.8 1.29 1.22 TOTAL 34 34 21.4 22.5 1.59 1.51 Leukemia-all subtypes except CLL: Males 19 19 9.4 9.2 2.02 2.07 F em al e s 8 8 7.6 7.8 1.05 1.03 TOTAL 27 27 17.0 17.0 1.59 1.59 Leukamia-Hyelocytic only: Males 13 13 5.2 5.0 2.50 2.60 I l Fem al e s 6 6 4.8 5.0 1.25 1.20 TOTAL 19 19 10.0 10.0 1.90 1.90 i
1 ~ E.R.I. Page 13 September 11, 1987 IV. CRITIQUE OF 'tHE MDPE ANALYSIS In the report issued on March 16th the MDPH presented data from 24 twns that lie approximately within a 20-mile radius of Pilgrim I. The MDPH report focused on five coastal twns near the plant - Plymouth. Kingston. , Marshfield. Duxbury and Scituate - chosen because of "their proximity to the Pilgrim plant, area topography, and coastal meteorological conditions" (p.1). Pilgrim I is located in Plymouth. The other four twns lie northward along the Atlantic coast. The hypothesis that resulted in the selection of the five twns relies on the supposition of a "' circulating' pattern of air" that would be created by the tecperature diff erential between land and sea masses and that would trap radiation from Pilgrim I and continually expose coastal residents to it. To date. the only meteorologic reference cited by the MDPH is a drawing entitled "Land and sea breezes." f rom DA Frank Field's Weather Book.7 No meteorologie data or measurements of emissions or envirereental radiation levels in the geographic sea around Pilgrim I have been used, despite the ackncvledgement by the MDPH that large amounts of such data are i availabl e. In the absence of any data supporting this particular selection of twns to study, we have chosen to expand the analysis to include other twns in the vicinity of Pilgrim I (see Section 7). l i l If there were an environmental exposure producing a geographically 1 localized increase in a disease rate, we would expect to find the same or a j greater increase in the incidence rate among women than among men. because 1 1 1 I
E.R.I. Page 14 September 11, 1987 of differences in exposure that might be experienced in each group. Data based on 1980 census figures and prepared by the Data Resource Center of Boston ' Central Transportation Planning reveal that for the five-town area studied by the EPH, 81% of males over age 16 work outside the home, in contrast to 51% of f emales. Of those whc were in the workforce in 1980, 64% of men and 45% of women who lived in the five-town area worked outside of that area.3,8 Thus, 77% of women but only 48% of men who lived in the five-town area in 1980 remained in that ares during the work week. Theref ore, adult women (and, of course, children of both sexes) would receive a greater share than adult men of any hypothetical exposure that was geographically localized in the five towns, and would sustain a greater ( effect if that exposure increased the incidence of one or more types of leukemia. v When viewed in light of previous studies of the effects of exposure to ionizing radiation, results of the five-town analyses suggest that radiation exposure is an insufficient explanation for the elevated leukemia rates in this area. Studies conducted in the UniteI tingdom have indicated possible excesses of leukemia in children, but not of adults, living in the vicinity of nuclear power generating f acilities.9.10,11 3t,1 ,gte,t ggg,eg, og Ionizing Fadiation (5EIR) and Radicepidemiological Table reports also bdicate greater relative risks for leukemia due to radiation exposure among children than among adults.2.5 By contrast, neither acute lysephocytic leukemia in particular (Table 2) nor non-chronic-lymphocytic leukemia in general (Table 3) was eleveted among children in the five towns selected by the E PH. Adult males, but not females, in the five towns had elevated
E.R.I. Page 15 September 11. 1987 rates of eyelocytic leukenias and of all other non-chror.ic-lymphocytic leukemias considered as a group (Table C . Tae elevated rates of chronic and acute myelocytic leuke:ias among men were the most pronounced and statistically stable, as indicated by the comparative widths of the confidence intervals for these leukemia types. TABLE 2 Observed and Espected Incidence of Acute Lymphocytle Leuksala Among Residents of the Fiva Towns Selected by the NDPH. r by Age (0-19) and by Sex, 1982-1984 t
-Cases- 90% Confihnce Sex Obs erved Expected SMR Interval ,
Male 2 1.42 1.40 0.34 - 4.01 Female 0 1.04 0.00 0.00 - 2.21 Both 2 2.46 0.81 0.20 - 2.31 e e
l E. R. I . Page 1 September 11, 1987 ) l i TANLI 3 Observed and Erpected Incidence, of All Lenkamiss Racept l Chronic Lymphocytic Lenkania among Residents of the ! Tive Towns Selected by the EN by Age and Sez. 1982-1984 i I Cases- - - - 90% Confidence Age fm Obsewed frpe.ted SMR Inten al 0-19 Males 2 1.92 1.0A 0.25 - 2.96 1 Fe sles J 1,.43 0.67 0.07 - 2.7 8 Both 3 3.41 0.88 0.29 - 2.10 [20 Mal ts 17 7.29 2.33 1,49 - 3.50 l l Temale s , 7, 6,.), 4 1,J,0 0,,,. 5,6,. - 1. 9 8 i Both 24 13.63 1.76 1.21 - 2.48 i l All Males 19 9.21 2,06 1.35 - 3.0'.4
? uales 8 7.62 1.02 0.55 - 1,77 Both 27 17.03 1,59 1.12 - 2.19 I
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l l l l 1 E.R.I. Fage 17 September 11. 1987 l 1 l I TMLE4 Observed and Espected Incidence of Leukastia Among Adult Residents (Age 120 Years) of the Five Tomms Selected by MDFE, by Lookemia Type end Sex. 1982-1984 l Leukemia --Cases - 90% Confidence Type Sex,' Obs erve d Expected SMR Interval Chronic Male 3 1.13 2.66 0.89 - 6.34 syelocytic Female 0 0.97 0.00 0.00 - 2.37 Both 3 2.10 1.43 0.48 - 3.41 Acute Male 9 2.86 3.15 1.75 - 5.30 myelocytic Fenal e 4 3.29 1.22 0.48 - 2.60 Both 13 6.14 2.12 1.31 - 3.28 j
. f '
other Male 1 0.62 1.62 0.16 - 6.63
- yelocytic Fecal e J2 0.40 2.48 0.25 -10.28 Both 1.02 1.96 0.48 - 5.58 Total Male 13 4.60 2.82 1.74 - 4.37 orfelocytic Female J 4.66 1.07 0.48 - 2.13 Both 18 9.27 1.94 1.25 - 2.88 Other Hale 4 2.68 1.49 0.59 - 3.20 rion-chronic- Female 2 1.68 1.19 0.29 - 3.39 lymphocytic Both 6 4.36 1.38 0.66 - 2.59 Tot:1 Male 17 7.29 2.33 1.49 - 3.50 non-chronic- Fem al e 7 6.34 1.10 0.56 - 1.98 I l
lyw-hocy tic Both 27 13.63 1./6 1.21 - 2.48 l 1 l I 1 l 1
1 E.R.I. Page 18 Sept ember 11, 1987 Our comparisons of the SMRs in Tables 2-4 would not be valid if the distributions of age, race or ser d.4,f fered substantially between compared 3rcups and if any or all of thest f actors modified the eff ect of some er.use or cau.es of leukemis associated with living in the five-town area. The reason f or this possible lack of comparability is that each SMR is, in I l principle, standardized to a different distribution of these variables. We checked these distributions and found them not to diff er appreciably. In particular, the distributions of race and sex are virtaa11y identical in the age groups we have compared, as are the distributions of age and race in the comparisons between men and women. Consequently, these results would not change appreciably if the rate ratios were standardized to identical i distributions of these variables. l I l l l
E.R.I. Page 19 Sept ember 11. 1987 l Y. RADIATION DONES FREDICTED FROM RADIOEFIDEMIOLOGICAL TABLES i l The NIH Radicepidemiological Tables can be used to compute the ionizing radiation dose that would produce a given increase in incidence, such as
)
the SMR of 1.59 for all non-chronic-lymphocytic leukemias in Table 3. The Tables predict the probability of causation (PC) of cases of leukemia in people ef given ages who were exposed to certain doses of low-LET radiation (1.10. or 100 rad) at given ages.2 (These predictions are based on studies in which doses were received at higher dose rates than in the population i near Pilgrim I.) To take a single example. Table PC-1-C-30 gives a probability of causation (PC) of 28% for a man diagnosed with a non-l f chronic-ly=phocytic leukemia at age 35 af ter having received a dose of 10 rad at age 30. We shall use this Table and the other Tables for non-chronic-ly=phocytic leukemias to compare the predictions with the MDPH results fcr the five-town area. The PC, also known as the attributable proportion for the exposed population.12 can be azpressed as a direct function of the incidence rat (. ratio (RR): 1 RR - 1 PC = (1) RR . 1 i
E.R.I. Page 20 Sept ember 11, 1987 We can rearrange this equation to express the RR as a function of the PCs
- 1 1
RR = (2) 1 - PC ( Thus, PC = 28% in the example above corresponds to RR = 1.39. The tables i therefore predict that a study of a group of men age 35 who received a dose
! 10 rad at age 30 would produce an RR of 1.39 for non-chronic-lymphocytic i leukemia. i
- l l The PC may be viewed as the proportion of a group of arposed cases that is attributable to the exposure. An analogous measure is the attributable proportion for the total population (APT ), which is the proportion of a group of exposed and unexposed cases that is attributable to the exposure.12 One expression f or this measure is a combination of the RR and the exposed proportion of the population (P,): i i P, (RR - 1) j APT * (3) P. (RR - 1) + 1 ! l 1 l l 1 I i i
E. R. I . Page 21 Septembe r 11. 1987 We can rearrange this eque. tion to express the RR as a function of the APT sad the P,: AP7 - (AP;/P ) - 1 APT-I We used equations 2 and 4 to ccepute the SMR that the Radicepidemiological Tables would predict for the population of the five-
*mn area if all or part of that population were to receive a dese of 1.10 or 100 rad. (The SMR is a standardized RR. standardization being a way of , I controlling confounding by such f actors as age.) To do so, we assu=ed an average induction time of eight years, corresponding to the interval between 1975 and 1983. (We chose 1975 as the time of exposure in this illustrative computation because several MDPH authors expressed interest in an exposure period ending in 1975.13'14 We chose 19fs3 as the end of the induction period because 1983 is the midpoint of the three-year interval for which leukemia incidence data are available.) To simplify the computations, we applied the Radioepidaniological Table for exposure at age zero to the person-time in the five-town area for ages 0-9. the Table for exposure at age 10 f or the age-group 10-19. etc.
To see how the computations proceeded, consider males in the age group 0-9 and a dose of 1 rad. Radioepidemiological Table PC-1-C-0 gives 4 PC = 13% for cases occurring eight years later (corresponding to the eight-l year induction time assumption). With equation 2. we obtained RR = 1.15. i 1
E.R.I. Page 22 September 11, 1987 From the age- and sex-specific rate for the rest of the Coemonwealth, we obtained an expected number of 1.16 cases in this stratum f or the five-town area. We multiplied this number by the RR to yield a predicted number of 1.33 observed cases. Af ter repeating these computations for all categories of age and sex, we added the expected numbers together and we added the predicted-observed numbers together. The predicted-observed total divided by the expected total equals the hypothetical SMR that the Radioepidemiological Tables predict would be produced in the five towns, eight years af ter the population of the area received an average dose of I rad. We then repeated the entire set of calculations for doses of 10 rad and 100 rad. The results are as follws: DOSE PREDICTED SMR 1 rad 1.11 10 rad 1.50 100 rad 8.80 These predictions should be compared with the observed SMR cf 1.59 obtained by comparing the five-town area to the rest of the Connowealth (see our Tables 1 and 4), nis comparison is premised on tne hypothesis that the average radiation dose was sustained by all members of the five-twn areas it indicates that the average dose would have been approximately 10 rad. no MDPH has assumed, hwever, that exposure occurred in only a subset of this population in its proposal to conduct a case-control study
E.R.I. Page 23 September 11. 1987 restricted to the five towns.15 (Without this assumption, the proposed ' 4 study would contain no unexposed people.) n e assumption of restricted i exposure was explicitly made by Dr. Sidney Cobb and several MDPH co-authors.14.16 who claimed to have found a four-mile by twenty-alle area within which the entire excess of non-chronic lymphocytic leukemias was confined. We do not know what proportion of the population of the five-town area ! lives in the four-by-twenty mile strip. Neither can we predict the 7-oportion that would be classified as exposed under alternative exposure hypotheses. We can, however, use equation 4 to compute the RR that would
, correspond to any given exposed proportion. P.. of the population in those 5 t owns. For exa=ple, we can see f ree equation 4 that if P, a 1.00 (i.e. the j entire population is exposed). then:
-1 1 RR = ---- -- = ---
M;-1 1 - M; J Ccsparing this expression with equation 2. we can see that when P, = 1.00 AP; = PC. ) Another expression for the AP; is as fo11ews:12 , l
- l 1
I; - Io
! M. =
I T l I 4 I l l 4 l l 1
E.R.I. Page 24 September 11, 1987 where ITis the rate in the total population of exposed and unexposed people [ and Io is the rate among unexposed people. { We can divide the tot and bottom portions of the right-hand side of this equation by Io to obtain the follwing expressions (I7/Io ) - 1 SMR - 1
=
AP7= IT/IO SMR ne quantity. I T/IO is equivalent to the SMR comparing the five-town arsa to the rest of the Ccemonwealth, under the assumption that only part of the population of the five-town area is trposed. Thus, the SMR of 1.59 for the i five-twn area as a whole corresponds to APT = (1.59 - 1)/1.59 = 0.37, or 37% of the cases in the area hypothetically attributable to the exposure. If only half of the population was exposed. P. = 0.50 and, according to
, equation 4. RR = 2.18. his value is the predicted RR that the case-control study proposed by the MDPH would estimate for the exposed subset of the
- population of the five towns, if the apparent excess were in f act attributable to the arposure. The value of this RR would not change if the study were expanded to include other tevns, because under this exposure i .
hypcthesis the enlargement of the study would merely add to the size of the
- unerposed portion of the population.
We have calculated the predicted RA that would be estimated for the exposed subpopulation of the five twns, assuming a wide range of values for i the proportion of the population of the twns that is classified as exposed. 1
, E.R.I. Page 25 September 11, 1987 These are shown in Table 5. If the exposed proportion (e.g., within the four-by-twenty mile strip described by Cobb et al.) is as low as five per cent of the everall populstion in the five towns. the corresponding RR would be as great asp 12.78.
4 We can now compare these RRs to the predicted SMRs we computed for the five-tewn ares from the Radioepidaziological Tables (see page 20 above). The Tables predict that, if the entire five-town area were exposed to ionizing radiation responsible for the estimated SMR of 1.59 for that area, i the radiation dose would have been on the order of 10 rad per person on everage. The smaller the subset of the population for which the average dose is computed, the higher the RR and the higher the corresponding (
- everage dose to that subset that would be predicted by the Radioepide=iological Tables. Ao noted above. the RR of 1.59 under the assumption of P = 100% corresponds to about 10 rad per person. The Tables
*.. 1 predict an RR cf 8.8 for an everage dose of 100 rad. This RR corresponds to a P, of 8% (see Table 5). Although the four-by-twenty mile strip identified by Cobb et al. may contain isss than 8% of the area's population, it seems saf e to conclude that the elevated liukemia incidence rate in the five towns corresponds to an everage dose of 10-100 rad per person accordins to the Radioepidemiological Tables. ! l l
i l l i i I l 1 1 l I
l
- E.R.I. Page 26 Sept ember 11, 1987 i
1 I l TABLE 5 l l Rate 'tatios (RA) Correspondd.ng to Different . Erposed Proportions (Fe) in a Total Population (Exposed and j Unexposed) 'sith an Attributable Proportion (AFy ) of 371 ) l
~
P, (%) KR* _ .__z _ - 100 1.59 ( 10 rad) i 95 1.62 1 90 1.65 , 80 1.74 i 50 2.18 20 3.94 i 10 6.89 8 8.80 (100 rad)
. 5 12.78 ,
i __ ___
- The RR4 that would be produced by ionizing radiation dose l 1evels of approxi=ately 10 and 100 rad, according to the Radicepide=iological Tables, are indicated.
I ~ We have no kncviedge of any attempt to estimate quantitative exposure levels corresponding to the circulating-wind hypothesis proposed by Dr. Cobb and the MDPH. It is our understanding, however, that this hypothesis would predict average doses at least two orders of mag .itude lower than 10-100 rad per person. There are several uncertainties and assumptions in the computations we have made with the Radioepidaniological Tables. Nevertheless, the predicted doses are so high that one of two conclusions must be true. One is that the
\
Tables underestimate the ef fect of low-level ionising radiation at low dose i
E. R. I. rage 27 September 11. 1987 rates on non-chronic-lymphocytic leukemias by at least two orders of magnitude. Because the Radioepidemiological Tables are based on studies in which observed radiation doses were in the range of 10-100 rad, this first conclusion would imply that radiation doses dif fering by several ceders of magr.itude (but received at different dose rates) produce the same increase in leukemia incidence. The second conclusion is that ionizing radiation from Pilgriz I cannot be responsible for even a esall proportion of the 59 per cent elevation in incidence reported for the five towns as a whole. t e j i l
l l l l l E.R.I. Page 28 September 11. 1987 l l VI. LEWCEMIA RATES IN RELATION 10 FRO 1IMITY TO PILGRIM I Given the current 1.2ck of an aposure assessment scheme based on meteorologic and envirormental radiation monitoring data for the environs of Pilgrim I. we off er as an alternative to the circulating-wind hypothesis the standard approech of gres. ping tevns solely on the basis of proximity to the t plant. he tevns of Duxbury. Kingston Plympton. Carver and Plymouth f orm an approximate semicircle around the plan * 'u a radius of abou.13 miles. We place these tcvns into Zone I .. x .i
'),
j ne next set of eight tcves i-- Marshfiald. Pembroke. Hanson. Halif ax. Middleboro. Wareham. Bourne and Sandwich - lie within a ring for=ed by adding a second semicircle approxir.ately 17 miles f rom Pilgrim I. We call 4 these tcwns Zone II. j ?. 1 one III consists of the remaining 11 towns on the list compiled by the i CPH. As shwn in Figure ?.. Zone III is somewhat patchy. It might have l been advisable to include 14eville. Mattapoisett, and Talmouth in this , i zone. Because these tcwns. were not on the origins 1 ETH list, we did not obtain data for them from the Cancer Registry. Zone IV is the remainder of the Commonwealth of Massachusetts. l i h
)
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E.R.I. Pess 29 Septerabe r 11 1987
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. E.R.I. Page 30 Sept ember 11. 1987 Table 6 shows our comparisons of leukemia rates for all four zones. We t used Zone I7. the f arthest zone f rom Pilgrim t. as the reference category.
An incidence rate ratio (RR) of 1.00 is arbitrarily assigned to this zone. The RRs for the other zones indicate the relative degree to which the rate in each zone axceeds or f alls short of the rate in Zone IV. The RRs in each , row of Table 6 are "directly" standardized (SRR) to the age distribution in l Zone I7. An eff ect that would steadily decline with distance from the plant weuld be indicated by a steadily increasing set of SRJs f ree Zone I7 to 1 4 Zone I. i As shown in Table 6. the rates in Zones III and I7 vere very similar f or every type of leukemia exa=ined except f or childhood acute lymphocytic ,
- t I ,
leuke=ia. for which the rate in Zone III exceeded the rate in Zone I7 by 30% I (SRR = 1.3 0) . For all leukemia types in Table 6. the rates in Zones I and II more closely resembled each other than did the rates in the other two j s l zones. The rate of childhood acute lymphocytic leukemia was depressed and l l } the rates of the other leukemia types among adults were somewhat elevated in I Zones I and II. The proportional elevation was greater, nearly a 50% excess. ter all eyelecytic leukemias as a group than for other leukemia subtypes. I a I
- I l
J I i i
E.R.I. Page 31 Septembe r 11. 1987 t TABLE 6 Directly Standardisee Incidence Rate Ratios in Zones of Prominity to Pilgrim I*, by Age and Leukemia Type, 1982-44
- .; =
Leukemia ----Proximity Zone *----- Type Age IV III II I
.s.
Acute lymphocytic 0-19 (1.00) 1.30 0.75 0.60 Chronic myelocytic 120 (1.00) 0.95 1.93 1.44 Acute myelocytic 1,20 (1.00) 1.18 1.38 1.42 ( ,/' Cther eveleeytic (20 (1.00) 0.61 0.97 1.47
\..
Total myelocytic [20 (1.00) 1.13 1.46 1.46 Other
. non-chrorie-lymphocytic 1,20 (1.00) 0.88 1.26 0.95 Total non-chronic lymphocytic L20 (1.00) 1.01 1.39 1.29
*See Tigure 2
E.R.I. Page 32 September 11. 1987 j To simplify these computations, we made a comparison between the 13 twns in Zones I and II and the 11 towns in Zone III, leaving the remainder of Massachusetts nut of the analysis. his dichotomization of the 24 towns selected by the CPH divides the person-time in this geographic area approximately in half and imprwes comparability by removing the influence of any dif ferences that might exist between this part of the Commowealth and such areas as Boston and Western Massachusetts. l j Table 7 shows the results of this analysis. The rate of childhood scute ly=;hecytic leukemia in Zones I and II is only half the rate in Zone ; III. Ameng adults, the total elevation of all non-chronic-lymphocytic
,, leukemias is not as great as in the five-tcwn area defined under the i r j
exposure hypothesis of Dr. Cobb and the CPM (Tables 3 and 4). h ere are j diff erences within this category as well. he rate ratio in the MDPH five-1 ; 1 town area was greater for myelecytic leukemia, whereas types of leukemia , I .- other than myelocytic leukemia were in greater axeess in Zones I and II. ne disparity by sex appears to be present for syelocytic leukemia (an elevated rate among non but not women) but for the other non-chronic- , I lymphocytic leukemias there is an indication in our analysis of a greater elevation among vesen than among men. nese estimates are very irprecise, as indicated by the confidence intervals in Table 7. When all adult, non-
! chronic-lymphocytic leukemias are considered as a group, there is little if any disparity by sex.
4 i'g As in our analysis of the data for the five towns selected by the NDPH. l we confirand that the distributions of the stratification f actors were 4 l
l l l l l E.R.I. Page 33 Sept ember 11. 1987 '
)
l nearly identical between the subpopulations for which we compated SMRs. In addition, the comparison of SMRs to "crude" (i.e. unstandardized) RRs in l l
"hble 7. indicates littla confounding by age or sex. Thus, we computed J
confidence intervals f or the crude RRs. TABLE 7 ^ Crude Rate Ratios and Selected DOta Camparing Zones I and II with Zone III by Age and Sex ; i __ i Leukemia Age Sex Crude Rate Ratio
- 90 Confidenc e l Type Interv al
( Acute ly=phocytic 0 - 19 Both 0.53 0.15 - 1.83 (0.48) Tot al L 20 Male 1.22 0.63 - 2.37 syelocytic Tes ale 1.05 0.43 - 2.54 Both 1.16 0.68 - 1 .97 j (1.18) J 1 Other non- L 20 Male 1.15 0.40 - 3.31 ) chronic- Fem al e 3.14 0.55 - 17.91 i lymphocytic Both 1.55 0.o3 - 3.78 (1.69) j Totsi non- t 20 Male 1,20 0.68 - 2.10 chronic- Fem ale 1.34 0.62 - 2.93 l lymphocytic Both 1.25 0.79 - 1.98
- (1.29)
_ _.=
- Selected SMRs in parentheses j
( t + t
, E. R. I. Page 34 September 11. 1987 These results differ in some ways from those obtained under the MDPH exposure hypothesis. Under the circulating-wind hypothesis proposed by the MDPH. there is a clear difference by sex among adults. with only men having an elevated rate of eyelecytic leukemia. This observation, as neted above.
is f.nconsistent with an effect of domiciliary environmental exposure. Under the proximity-based exposure hypothesis. on the other hand, the association among adults is not restricted to men. This observation f avors the proximity-based exposure scale under the causal hypothesis.
"he estimated incicence rate ratios are icwer using the proximity-based exposure scale than under the circulating-wind hypothesis. By corresponding to icwer predicted radiation dese, these observations put the proximity-t i based scale slightly more in line with existing theory and data (as represented by the NDI Radicepidemiological Tables) than the circulating-
, vind hypothesis. Nevertheless, the estimatad rate ratios still correspond l to predicted exposures that tre stuch higher than vould be expected under any quantitative exposure hypothesis based on tadiation monitoring data and meteorology in the geographic area near Pilgrim I. The estimated rate ratio
; of 1.25 for all non-chronic-lymphocytic leukemias in Table 7. for example, j
] I l corresponds to a dose of 1-10 rad according to the predictions free the ' Radicepidemiological Tables (see page 20) and the computation of an average l l dose for all residents of Zones I and II. An even higher dose vould be i j predicted if the average were computed for a subset of this population, I i i ] Under either exposure hypothesis, however, there is either no increase l 1 or even a deficit of acute lymphocytic leukemia among children in towns that l
=. = - - . - . - - - .. _ . . . .. .. - . - _ - -
l E. R. I. Page 35 September 11. 1987 ! are hypothesiaed to have received greater degrees of enviremental radiation orposure. This observation is inconsistent with a causal interpretation in
- terms of radiation released from Pilgrim I to the general environment. ;
i The comparatively high rate ratios and the restriction of the elevated rates to .dults in these analyses tend to run counter to the hypothesis of I environmental radiation exposure. On the other hand, these observations 4 l sight be predicted by hypotheses concerning occupational exposures to I { 1eukemogens. Such exposures would include ionizing radiation and industrial ' i
... m . . : ,a .. bencene.
} l l Tree the data available thus f ar. it would be prudent to concentrate available resources en developing and implementing an in *epth occupational e:q:osure assessment plan for the case-control study the CPH 1: planning. A . I ! complete occupational history should be obtained for all cases and controls. ' i..
- Imployers should be contacted for detatis of the work history of each 4
individual. Workplace exposures to ionizing radiation, becaene, and other j l industrial solvents should be emphasized. Such exposures are more promising 1 ) j explanations for the observed pattern of leukemia rates in this part of 1 j Massachusetts than any hypothesis of widespread enviromental exposure to l ionizing radiation. i 1 i l
)
l l 4 1 2
E.R.I. Page 36 Sept ember 11, 1987 VII. REFERENCAS
- 1. Health Surveillance of the Plymouth Area. Massachusetts Department of Public Health Center for Health Promotion and Environmental Disease Prevention. March 16, 1987.
i
- 2. Report of the Nattenal Institutes of Health Ad Hoe Workins Group to Develop Radicepidemiological Tables. NIH Publication No. 85-2748 January 4 1985.
- 3. 1980 Census of Population. Volume 1. Chapter 3 Part 23. Buresu of the i Cens u s . U.S. Department of Commerce. June,1982.
I ~ 4 Pre isie.21 ?:rtiatien Pro 4ections: 1985,1990 and 1995. Cities and Towns in Massach asetts. Massachusetts Institute of Social and ] Economic Research. June,1986.
- 5. The Ef f ects on Populations of Erposure to Low Levels of Ionizing Radiation. Cazeittee on the Biological Ef f ects of Ionizing Radiation. Washington, D.C. : National Academy of Sciences, 1980.
- 6. Miettinen 05: Standardization of risk ratios. Am J Epidemiel 1972:96:383-8.
] 7. Field P: Dr. Frank Field's Veather Beck. New Torkt ! G. P. Putnam's Sons 1981. 2
- 8. Data prepared by the Data Resource Center. Boston Central '
I j Transportation Planning Staf f, June 3,1987.
)
i 9. Beral V: Cancer near nuclear installations (letter). Laneet. 1987 i:556. I
- 10. Darby SC and R Doll: Fallout, radiation doses near Dountasy, and childhood leukaemia. Be Med J 1987 294:603-1.
1
E.R.I. Page 37 Sept ember 11. 1987
- 11. Roman E. V Peral. L Carpenter et als Childhood leukaemia in the West rkshire and Basingstoke and North Hampshire District Health Authorities in relation to nuclear establishments in the vicinity. Er Med J 1987:294:597-602.
I
- 12. Rothman KJ: Modern Epidemiolery. Boston: Lit tl e.
B r own & Co. , 19 86, pp. 3 8-3 9.
- 13. Walker 3 and DM Gute: Testimony before the Joint Committee on Energy. Commonwealth of Massachusetts, July 31. 1986.
- 14. Cobb S. RW Clapp, CK Chan. 3 Walker: Leuke=ta in five Massachusetts coastal towns (Abstract). American Epidemiologic Society. March 18. 1987.
{ l
- 15. Study Proposait Case-Control Study of Leukemia in i' a Towns-The Plymouth Area. The Massachusetts Department of Public
, ,' Health. The Division of Environmental Epidaziology &
Toxicology. January 16, 1987.
- 16. Cobb S t Testimony bef ore the Joint Committee on Energy.
Commonwealth of Massachusetts. March 24. 1987. i l
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=__ _ _ = :esasr-E a E mE a For your in"ormation F EDISON Pilgrim Nuclear Power Station nwy nn nur mmourn, Ms 0236r February 9, 1988 88-12 EIGHT NEW OPERATORS RECEIVE NRC LICENSES AT PILGRIM Plymouth, Mass. -- Ralph G. Bird, Senior Vice president-Nuclear for Boston Edison Company, announced today that six Raactor Operators and two Senior Reactor Operators have received their licenses from the U. S. Nuclear Regulatory Commission.
This is the second class in a row to have a 100b pass rate. The eight of licensed new Operators Reactor operating personnel bring to 22 the number Senior Reactor Operators (SROs) (ROs) and to 26 the number of at Pilgrim. Last i'uly, eight new Ros -- out of eight who took the examinations -- were added to the ranks, doubling the complement at that time. As a condition of their licenses, the new ROs and SROs must complete five major control manipulations in the control room after Pilgrim restarts, and they must spend one month on watch than 20under percent supervision power. After while the plant is operating at more they have completed those requirements, the license conditions will be lifted. The NRC operator licensing examinations taken in December 1987 lasted three days and consisted cf a six-hour written section followed by approximately six hours of oral and performan:9 examinations in the plant and on the plant-specific control room simulator in the Chiltonv111e Tr&ining Center. To pass the examination, a candidate must have an overall gradesof 80 percent. The examination such areas as mathematics, followed a year of classroom training in chemistry, reactor theory, heat transfer, health physics, fluid flow and all plant systems. The candidates also stood watches under supervision in the plant's main control room and spent time on Boston Edison's full replica control room simulator. The two SPO candidates received additional administrative training in control room man &g.Jont .ri requirements. All of the ne,> reactor operators and man'ir remctor operators in this class are veterans of the J.T- Nav,, where they received nuclear power plant tr' aing ari opers' tag experience in the Navy's nuclear po. . program. 440 v - . - w ., m ww
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l Exemption #13 This exemption was requested from the requirement to have fire resistant protection to structural steel members supporting fire barriers in fire zone 1.30A that are separating redundant trains of safe shutdown equipment in the , reactor building in fire zones 1.9 and 1.10. ' I i Evaluation to support BEco's conclusion that this exemption will not present undue risk to the public health and safety was provided in BECo letter 86-110 dated 7/28/86. However, by telecons dated 9/22/86 and 10/1/86 BECo was i requested te address direct flame impingement from cable trays located directly bei w structural steel beams in the torus compartment which was not addressed in Geference 3. Based on a review of the raceway configuration with respect to the structural teams Boston Edison has decided to install solid top tray covers for the entire length of the cable trays to preclude any direct flame impingement from these capie trays to the unprotected steel beams, Bottom tray covers.will be t installed entending 3'-0" on both sides from the center of the beam where the tray crosses the beams to preclude any downward flame free reaching the steel beams, The recuired information is provided below. l l Qu_estion #1 Provide specific details pertaining to the tray covers, 1 j The attached sketches and catalog cuts provide the required information, i Question #2 I What actions will be put in place to assure that the tray covers once l installed will stay in place? BECo =til revise the surveillance procedure to include once an operating cycle surveillance of the cable trays and covers in the teru: ccepartment. l Question #3 What is the Cable tray fill? The cable tray fill is 16L The cab'es in the trays are IEEE 383 qualtfled and do not self propagate fire, Question sa Evaluation of how the tray cover will do the task of precluding direct flame impingement on the steel beams, Boston Edison will install top and bottom tray covers as desertbed ahove in order to prevent cable fire frce putting flames on the unprotected structural steel in the Torus Compartment. FOR FORV A7 OA CLY
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f r The continuous cable tray covers will obstruct vertical flame development.
& This will prevent vertical flame, expansion but it could create a downward flame that could pass out of the bottom of an open tray and lap around the sides of the tray. In order to prevent this "downward" flame from circumventing the top cover, i.e. thereby deflating the tray cover, a tray bottom cover will also be installed.
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The "bottom" cover will extend three (3) feet beyond the centerline of the beam on both sides. The combination of the top and 00ttom covers will probably restrict air flow to the burning cables. This will also probably extinguish a cable fire. However, BECo has conservatively assumed the cables to continue to burn even though the cables are IEEE 383 qualifted and that the covers will only function to deflect the flames to the end of the "bottom tray j cover". This will confine any possible flame in three feet to the side and , about 18 inches below the wide flanges and therefore prevent direct l tmoingement. l I ne believe this exemption is warranted and conforms with the special l 1 circumstaaces of 10CFR50.12(a)(2) as outlined below. . ) 10CFR50.12(a)(2)(lii): "Compliance would result in uncue hardship or other costs tnat are significantly in excess of those contemplated when the regulation was adopted." Upgrading of the entire structural steel beams in the torus compartment will, i create an undue hardship due to scheduling impacts and manpower expenditures.' The task will involve massive staging to support the effort and is expected to i take approximately 2 months to complete. The actual upgrading of the steel beams, after the staging is completed, is expected to take approximately 6 months costing about $2 million with substantial ALARA impact on the personnel implementing the task. Tnese costs are significantly in excess of those contemplated when the regulation was adopted. I 10CFR50.12(a)(2) tv): "The exemption would result in benefit to the public
- j health and safety that Compensates for any decrease in safety that may result from the grant of the exemption."
1 The task of upgrading the structural beams in the torus compartment will ] require massive staging which adds a considerable amount of fire loading to the area during the entire 6 months that it would take for the task to complete. This would present undue risk to public health and safety. 1 1 ,
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- 3. THE ONLY CABLE TRAY IN FIRE ZONE 1.30A 15 TRAY ;
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- 3. THE ONLY EA8tE TRAY IN FIRE ZONE 1.30A IS TRAY
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ap _ . . WI,/uk 7 Boston Edison Company f8/6 Anoendix R Exemption Reauest Status Number Description Suturittled to NRC Status ER #01 B CorerolRoom-trom prow 2ng a fuod 3/18/81 Letter 2.81.059 Grarted-leser fem NRC 11/1041 (1 A1 b suppression system ER #05 Torus Waer Level- Exerghon from Submmed Section 35 BECo. Lemor to Gransed ty NRC 6/1045 (1.85.191) PDC 8N' pmveng tre dmoction and automate NRC 6/25/82. ~BECo. Response to (Redundant) suppression in the Torus Cormartment Appendix R' i ! ER #06 Torus Waer T'ergerature CorNr:od with Torus Waer Level Grarmed - Combined wish Torus Waer Level Exemption Exernption Request submitted 5/17/83 Roquest #5. PDC 85-41 l (2.83.130) ER #07 Rearsor Buildmg Watsa Curtae (El Submetal Section 35. resubmmed Grarted by NRC (1 E4.379.1 E5.191). See PDC 23'-07 Exemption from providing an 3/11/83 (2.83.069). 5/17/83 85-049A and 0498 automatic fee suppressaon system (2.83.130). ItWo. 4/2/S4 (2E4.049), throughout fre zones 1.9 and 1.10 (225 057) (2.86.009) and (2E6.034) ER #08 Reactor Buibng Wmer Curtm(El SubmmW Section 35. resubmmed Grarsed by NRC (1E4.379.1E5.191). See PDC i 51*-0") Exerglion from provdng an 3/11/83 (2.83.069). 5/17/83 85-049A and 0490 ) automatic fire suppressaan system (2.83.130). Info. 4/2/84 (2E4.049). throughout fire zones 1.11 and 1.12 (2.85.057), (2.86.009) and (2.86.064). See Exemption Request #7 1 ER #09 Areas with asemate shutdom and no submas section 3.5. Restanced Grarsed - See NRC letters (1E4379 & 125.191) frxed firs suppression system 5/17/83 (2.83.130) ER #11 Lack of reed fire bamer between Torus 11/16s3 (2.83 281) on hold nor tray cover em dwion. tw dwion is being Cormartmers and the CRD Cuadrart 7/28/96 (2 86.110) revsewed by third party 11/14/86 (2.86.176) ER #12 Lack o' resed f<e bamer between Torus 11/1 983 (2.83 281) on hold sor tray cover cm azion. cm dwion is being Cormartment and the CRD Ouadrari 7/28/86 (2E6.110) reviewed by third party 11/1436 (2.86.176) I Page 1 June 26,1987 i eL O,
/ -
Boston Edison Company Appendix R Exemption Request Status Numtper Description SutunItted to NRC Status ER #13 unprosecsed SaucouralSteelin the 11/1643 (2.83281) on heks sermaycover+% c*Wis behis Torus Corepartmern 12/271s4 (244214) reveemmed by shms party 7/2ses (2.86.110) 11/1446 (2.86.176) ER #14 unpmeecsed StrucsuralSeest in the 11/1643 (2232s1) on hats serwar cover *W c* mis beme Seeam Tunnes 12/27s4 (224.214) motswed by sims parer 7/28e6 (2A6.110) 11/1446 (226.176) ER #15 No 3h fre herrterbeewoon Comdor Gmuped wth Esempelon Regaests la & 22. BECo.
#137 (FZ 3.9 perhal) out side she eigrHaff espected 7/1047 conputer room and Wie Radmasle Area (FZ 3.7) at B (-)1'-0* (IIIG2.6)
ER #17 Einergency LigNing Outsuse of the 2 87.e53 4/8/87 W 6t30e7-issued to pdRC. % h Process But$ing ER #18 Have nolprovided a 8ut 20 M of -EsseueE Geged auRh Exempton "4m 15 & 22. BECo. hodrontal dearance weicmA ireerverung SigrHaff eW 7/10e7 cornhusetsies. "A" train cables for the Service Water Pumps, RBCCW Purry ' and the "A* Diesel Fuel OE 7ransfer pungs are locasedin the acid neutrakring sump whichis part of Wie , WTR (B Fire Area 1.10) ER #20 unpmeeded ShucsuralSessiin the not ressired To be wreen as Ergneering Evaluahon FPEE #15 ceding of the Cable Spreadrg Room (wdlbe Erv .;;.4.v Evalualon-15) Page 2 June 26,1967
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O PREUMINARY CALCULATIEN SHEET C$ojiz,7,oyyobhh ;
' REV _DATE PAEPAAto sY DATE h . @ FINAL CHEcxto av E k OATEb/t2/B7 REV l DATR 7/22/87 SQ M y EDISON ,,, 2. o,15
SUBJECT:
M-300 Cable Fire Heatinc of Torus Compartment Ceiling Beams SR @ NSR , I 1.0 STATEHENT OF PRDBLEM Cables in an open tray raceway located within the Pilgrim Station Torus Compartment represent a fire hazard. An analysis is requiref to assess ; the magnitude and significance of this hazard. The particular ' motivation for this analysis is a concern for whether or not these fixed cable combustibles represent a fire hazard sufficient to threaten the integrity of the fire area boundary by causing the structural failure of , the ceiling support beams. This analysis is related to an exemption ' request (from the specific requirements of 10CFR50, Appendix R), No.13, ! originally presented in BECo letter no. 86-176, dated November 14, 1986 ' (U. The specific exemption request, no. 13, was revised in BECo letter 87-062, dated April 21, 1987 (2). 2.0 RESULTS AND RECOW ENDATIONS The analysis demonstrates that a fire consuming the cable combustiole materials in tray sections RP01 through RP07 will not cause the structural failure cf the torus compartment ceiling or any loss of ceiling integrity signif5 cant to its role as a fire arca boundary. , Specifically, steel beams that are required to support the ceiling, ! , including the loads on the floor above the torus compartment, will not l ! fait due to a fire involving the fixed combustibles in the torus j ! compartment. Therefore, there is no need to provide additional l protective measures for the ceiling beams, as described in Reference 1 1 (installation of cable tray cover). l l l l l 1 O l
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- 2M CN NO. O PREUMINARY
. nEv _ DAre memo., A s one WAy-3 nsu coeuo., eat oneahile7 nEv_.LDATE 7/22/87 g3[8Q$7DN gyn ,y gd oue N2/M WEDISON a,,,, s e ,y
SUBJECT:
H-300 Cable Fire Heating of Torus Compartment Ceiling Beams SR @ NSR [ 3.0 BUtiOO OF SOLUTION 3.1 The first method used to assess the fire hazard associated with the cables in the tray sections inside the torus ccmpartment was based.on the standard fire area combustible loading evaluation methed to determine the required fire resistance for materials of construction. Chapter 9 of Section S in the Fire Protection Handbook, (3) explains the fire severity and fire load ; concepts. Chapter 8 of Section 5 explains the concept of fire I resistance of structural systems, l The only significant fixed combustibles within tha torus compartment are electrical cables, and the largest concentration of exposed cables in the compartment are the cables in tray sections RP01 through RP07. The total heating value associated m with the combustible portions of the cables was divided by a
'- fraction of the torus compartment floor area, and this value was used to determine the equivalent duration of exposure to the i standard time-temperature environment of the testing furnace I specified in ASTH E119 (4). This equivalent exposure duration was then compared to the fire resistance values calculated for the various steel beam section shapes used at Pilgrim to support the torus compartment ceiling.
l 3.2 The second method to analyze the cable fire hazard was based on I a conservative estimate of the actual heat transfer that could l occur from a fire involving cables directly beneath a beam to the beam section enveloped by the fire plume. The heat release rates from fire tests involving similar cable materials were used, along with a conservative oveitstimation of the effectiveness of heat transfer from the fire gases into the l beam, to determine the maximum temperatures that exposed beam sections could possibly achieve. These temperatures were than compared to a critical or assumed failure temperature for the material. o
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- PRELIMINARY CA W LAT M SHEET $ $,237,0y yo PCM TE\.?AcM gq REV
, DATE_. TTeo CHAMCE PT.EPARED BY- DATE v b h X FINAL M M 7 ktY i
CHECKED BY oATE 7/2/07 REV 1 DATE 7/22/87 QQ f WEDISON an,,, 4 o,5
SUBJECT:
M-200 Cable Fire Heating of Torus Compartment Ceiling Beams l SR h l NSR [ 4.0 INPUT DATA AND ASSUMPTIONS rwo methods of analysis were used. The following input information ano a n umptions were used in the analyses, as noted: (1) conservatively assume that the cable fire consumes all of the combustible material in the cable design (both analyses); ,, (2) conservatively assume that the heating value for all of the combustible materials used in the cable design can be i represented by the total heat of combustion (as measured in a i calorimeter) of the material with the highaJt value -- in this . ~ case, the 11,000 8/lb associated with the Ckonite insulation [51 (both analyses) (3) there are no other significant combustibles in the torus m compartment (both analyses); (4) the initial and ambient temperatures are 100F (both analyses):
)
(5) the exposure of the beams to the fire is not concurrent with an earthquake - no seismic loads (both analyses); (6) structural failure is conservatively assumed to occur when the I ste?1 temperature within the exposed section reaches 1022F (first analysis, section 5.1 of this calculation) or 1100F (second analysis, section 5.3 of this calculation - this is associated with a reduction of yield strength for various structural steels of approx. 40% to 50% from their normal room temperature strengths (Reference 6); (7) conservatively assume that the beam section is totally exposed to heating by the fire - no part of its section perimeter is embedded or otherwise protected (both analyses); (8) conservatively assume that there is no heat transfer from the beam sEction to the ceiling or conduction to cooler sections of the same beam or other connected members (both analyses); 88 4 @ * @1 J & G4 PCAW NM
O PRELIMINARY CALCULATION SHEET eg r o
, REV DATE PREPARED BY oATE
' @ RNAL CHECKED BY k DATE- !T 07 REV__1_DATE 7/22/87 f%[8Q$7QM v,,vo ,y pg r. fg
'fniVEDISON ,,,,,,4o,3p
SUBJECT:
M-300 Cable Fire Heating of Torus Compartment Ceiling Beams SR b NSR (9) the beam sections are assumed to absorb heat originating from the combustion of material within the projected area of the beams on the tray sections -- for simplicity and to conservatively analyze the heat transfer into the most compact amount of steel, the beams and tray sections are assumed to always cross at 90' (second analysis, section 5.3 of this . - calculation); (10) the following baams are assumed to be required for the integrity of the torus compartment ceiling in its role as a fire area boundary or fire barrier (both analyses) - from Reference 7-
- H30 x 99 H30 x 172 H30 x 210 m H36 x 170 H36 x 230 H36 x 300 (11) conservatively assume that the total mass of cable combustibles is determined by the cable weight less the summation of the conductor weights, using the weight of solid copper wire instead of the actual class B, stranded conductor weight (both analyses)
- from References 8 and 9.
5.0 CALCULATIONS AND ANALYSES _ 5.1 The combustible loading of the torus compartment can be conservatively overestimated by dividing the heating value per unit length of the most heavily loaded tray section by one half of the minimum compartment width around the torus (i.e., the largest heat release potential per unit length of tray divided by the minimum half-distance between the compartment walls on oppsi* e sides of the torus axis). The cable material heating pot;*:t,al is derived from the information provided in References 5, 1, 9 and 10. The most heavily loaded tray section in the fire area is RP01, containing the cables presented in the table below, from Reference 10: No. of Cable No of Conductor Cable Cable weight v _ Cables Code = Conductors Size (AWG) 00 (in) (Ib oer ft) 26 212 2 12 0.49 0.141 2 312 3 12 0.52 0.155 1 712 7 12 0.71 0.329 L.= . i c. w mo
8 CALCULATION GHEET Cgo rw 9o O PRELIMINARY PER TEt.Ecod
. REV DATE -dffo cHRNGE . PRETARED BY ,
- oATE --
, FINAL M7 CHECKED BY_ bM oATE 20!@k REV._1._DATE 7/22/87 gQ g ,g gfg giisiVEDISON r,m,,1 c, ,3e.--
SUBJECT:
M-300 Cable Fire Heating of Torus Compartment Ceiling Br ns The combustible loadings of the tray sections were determined by subtracting the weight of the copper conductors from the total SR % weight of the cables residing in the tray. The weight of solid NSR [ copper conductor, with size designation of 12 AWG, was obtained from Reference 9. For the most heavily loaded tray section, kP01, the combustible loading was determined as follows: copper conductor weight, 12 AHG = 0.0198 lb/ft total number of conductors - 26(2) + 2(3) + 7 - 65 . - total cable weight - 26(0.141) + 2(0.155) + 0.329 - 4.305 lb/ft , total combustible material weight - 4.305 - 65(0.0198) = 3.018 lb/f t The most heavily loaded tray section, RP01, containt 3 lb/ft of m, combustible materials. The torus compartment geometrical information was obtained from Reference 7. The sketch below Mrtrays the minimum distance between compartment walls used in this analysis: l YW, [6MW& Wk
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CMMEM MU C PRELIMINARY $$ization o. REV DATE PREPARED BY DATE E FINAL CHECKED SY hdk DATE 7 D!E~7 REV._1_DATE 7/22/87 AE8 BOSTON .,,vo av #E oA1, 7/u/o l
$5sVEDISON ss,,,
SUBJECT:
M-300 Cable Fire Heating of Torus Compartment Ceiling Beams 7 c4
\
SR @ i NSR ; Using the higher heat of combustion, for the cable insulation, ' to represent the heating potential for both the insulation and jacket material, the linear heating potential is: l (3 lb/ft of tray) (11,000 B/lb) - 33,000 B/ft Using the minimum distance between the flats of the inner and outer torus compartment walls, and dividing that distance in * ' half to conservatively account for the area reduction due to the curvature of the room, the fire area combustible loading in the locality of the exposed cable tray is: (33.000 B/ft of tray) 21 ft - 2129 B/ft2 1 2 Using the approximate equivalence of fire loading and fire G severity (as represented by exposure to the standard time-L/ temperature environment in a test furnace) of 80,000 B/f t : corresponding to I hour [3], the torus compartment equivalent ' fire severity is: 2112 - 0.027 hrs. - 1.6 minutes 80,000 ' This serves to demonstrate the very "light" fire load that exists in thq torus compartment, where anything less than 100,000 t/f t" is usually considered to be a "light" or low fire load (31. j l V 1 a o . ioc, - e a ce ** **
O PRELIMINARY o ZATioN o. REV DATE PREPARED BY DATE b
@ FINAL CHECKED eY oATF. - , [I REV 1 DATE 7/22/87 M8Q$70M gppyg ,y__
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$WEDISON ,,,e, ? o, %
SUBJECT:
M-300 Cable Fire Heating of Torus Compartment Ceiling Beams I l SR [ l NSR The ability of fully exposed steel members to withstand exposure ; to the standard furnace tett environment is presented in Reference 6, on p. 138 in Figure 9.6. This figure is included in this calculation as Attachment 5. The figure shows that the exposure time before. failure (defined 7.s average steel section temperature of 550C or 1022F) is a monotonic function of P/A, the ratio of exposed section perimeter and cross-sectional i area. For the situation of concern in the Pilgrim torus ' compartment, the assumptions of full perimeter exposure and I failure at 1022F are conservative. L' sing the steel section properties obtained from Reference 11 for each type of beam used to support the torus compartment . ceiling to calculate a P/A ratio, and then using Figure 9.6 of Halhotra (Attachment 5) to determine the exposure duration before failure, the following results for fire resistance are ,S obtained:
--' 'oeam section P/A Exposure Duration (wide flange) ( i n )
- (m" ) to Fail (min.)
H30x99 3.44 135.4 14' H30x172 2.34 92.1 16 values are W30x210 1.93 76.0 18 approximate, H36x170 2.38 93.7 16 rounded to H36x230 2.01 79.1 18 nearest 1 H36x300 1.56 61.4 21 integer ! where, 9-2d+2bf +2(b f -tw), values presented in Att3chment 6. l Hith a fire severity or fire load of approx. 2 minutes, and a fire resistance in the steel supports of approx. 14-21 minutes, the fire area boundary integrity is not significantly threatened l by the cable fire. j i I n l
. . . , a m s.
i l O PRELIMINARY o ZADON NO._ REV OATE ho c, oK FREPAAED BY b oATE
@ FINAL OE 7f?2ff 7 CHECKED BYM DATE_7)22l87
,438 BOSTON REV_LDATE 7/22/87 A,rvo ey #3/ oAxe w ,
gisiVEDISON ,8,,, 9 o,3% ;
SUBJECT:
M-300 Cable Fire Heating of Torus Compartment Ceiling Beams ( SR h NSR [ 5.2 The smallest size beams, the H30x99 shape, are actually over tray sections RPO4, and RF05. These tray sections are loaded l l with fewer cables than RP01, and their combustible loading is determined below for the second analysis method. The cables presented in the table Delow are obtained from Reference 10:
~
no. of cables cable no of conductor cable weight code conductors size _(AWG) OD (in) (1b eer ft) l 22 212 2 12 0.49 0.141 l 1 312 3 12 0.52 0.155 - 1 512 5 12 0.65 0.270 As before, the copper conductor weight is 0.0198 lb/ft, m the total number of conductors is 22(2)+1(3)+1(5) - 52, i l the total cable weight is 22(0.141)+1(0.155)+1(0.270) - 3.527 lb/ft, and the total combustible material weight is 3.527-52(0.0198) - 2.497 or 2.5 lb/ft. The second analysis method is basically a simple and conservative approximation of the heat transfer process that actually occur if a fire could be established in the cable tray sections of concern. The approach consists of: (1) estimating the manner by which a fire involving the cable materials releases heat, i.e., the fraction radiated and the fraction convected upward by plume gases; (2) estimating the fraction of total heat released absorbed by the beam material; (3) estimating the flows of heat from the beam (into the ceiling, or to the air and ob
, by convection and radiation, respectively);
jects in the torus compartment I
%s
$$C4 PQHid M M
O PRELIMINARY o tZATioN NO. REV DATF ZEDARED BY- DATE
@ FINAL CHECKED BY- S DATE- 87 REV 1_DATF 7/22/87 A98BOS70N A,,yo ,v @V ur, uzi/n 1 9iEVEDISON ,,,,rio e gg
SUBJECT:
M-300 Cable Fire Heating of Torus Compartm'ent Ceiling Beams ! SR $ ) NSR 1 (4) estimating the redistribution of heat within the beam (conduction within the section and along the beam axis). To avoid a complex analysis, conservative and simplifying assumptions are made about the heat transfer mechanisms. First, 1 the beam section exposed to the heating by the fire is assumed - - to be perfectly insulatad from any heat sink - no renduction to ' the ceiling or the rest of the beam, and no heat losses by surface convection or radiation. Second, the heat released by I radiation is mostly intercepted by objects other than the t.eam .I and the plume gases impinge and envelope the beam directly above - the fire; therefore, the fraction of fire heat released that is absorbed by the beam is based on an estimate derived from the i heat release mode fracticns for the combustible materials. This l estimate is derived below. s The Okonite/0koprene cable combustible materials consist of: insulation - Okonite, formulation of ethylene - propylene rubber (EPR) jacket - Okoprene, formulation of neoprene rubbei , l EPRI funded tests at Factory Hutual Research Corporation of the l burning characteristics of cable materials, including these two I types of formulations. Each of these materials was tested in ' combination with another type, but an estimate can be made of their burning characteristics together from the available data. Table 5-7 from Reference 12 (Attachment 7) provides measurements of 53% for radiative release fraction for XPE/ Neoprene cables (XPE designates cross-linked polyethylene). Table 5-land 5-2 from Reference 13 (Attachments 8 and 9) provide measurements and calculated va' ies to derive a set of radiative rclease fractions for various tests of EPR/Hypalon cables (Hypalon is a trade name of a chlorosulfonated polyethylene, or CleS PE). These values are: o v 3 0, im EIG4'W U
1 . CALCULATION SHEET C*#$zAnon u o. O PRELIMINARY REV DATE DGEPARED BY- DATE h
@ FINAL C,ECKED BY--- oATE 7! !$7 REV l DATE 7/22/87 JEhgQjJQN Ay,vo ,y g' o r, pffg SWEDISON ,8w n or36
SUBJECT:
M-300 Cable Fire Heating of Torus Compartment Ce' ling Beams SR h test. ID Radiative Release Fraction
- 10 0.61 NSR 11 0.86 12 0.46 l 13 0.55 14 0.63 The two materials involved in these iests that are not present in the cables of concern, XPE and C1.5.PE, were tested in . - l ccmbination themselves and found to have a radiative release )
fraction of 34% (from Table 5-7, Ref.12, AH. 7). Therefore, since the polyethylenes do not contrit:ute to radiation as much as the rubbers do, a cable constructed from EPR/ Neoprene l formulations would be expected to radiate significantly more ~ l than 50% of the heat released. ; 1 The conservative and simplifying assumption for the following l heat transfer analysis is that 50% of the heat released by total 7 combustion of the cable materials is absorbed by the beam. This 1_ . could be seen as assuming that radiation is only 50% of the heat and that this is not absorbed, but that 100% of the convectively released heat is absorbed. Convective heat transfer from a fire through plume gases to a solid surface is certainly not 100% effective - considerable amounts of hot gases will drift away from the region above the fire and begin to fill the upper elevations of the torus compartment. Since the cable trays are at least 9ne foot below the beams and the trays are suspended away from walls and other objects within the compartment, most of the radiation released by flames or radiating portions of the plume will be intercepted and absorbed far away from the beam section of concern. Considering that these cables would not be expected to burn as efficiently and completely as in the large-scale fire tests and calorimeter tests performed to obtain the release fraction and heats of combustion data, the assumption of 50% heat transfer to the beam section is conservative for this analysis. 4 v
' obtained from Radiative Heat Release Rate of Table 5-1 divided by corresponding summation of Radiative and Convective Heat Release Rates of Table 5-1 and Table 5-2.
... e n c. = ==
O lZATION NO O PREUMINARY REV DATE PGE?ARED BV DATE
@ FINAL CHECKED BY-- oATE___7/2'E/bf 8Q37Qk REV 1 DATE 7/22/87 ypyg ,y g[] gg/p EDISON ,,,,,1 ,g , g 7,
SUBJECT:
M-300 Cable Fire Heating of Torus Compartment Ceiling Beams SR NSR C 5.3 The temperature rise in the steel beam section is conservatively approximated by the energy absorbed int; the section material divided by the product of the material mass and its specific heat, or [ *r
% Coluf The energy absorbed into the beam section is conservatively assumed to be one half of the heat released by the fire conse:ning all of the cable combustibles in the tray within the m .,
projected area of the beam directly above the tray. The length l of tray directly beneath the beam is equal to the beam flange width, since the beam and tray are always assumed to cross at 90' angles. The tray is always one foot in width, and therefore, the beam section length is always one foot in length. Since the steel specific heat increases by almost 707. when it is heated from 100 to 1100*F, a temperature-averaged specific heat value is used. Thus, the expression becomes I hds M * [f Mt.
- 6 A%< &w
, kbs Mcwd,cuhis hs ANe.
% GM G
v a.gp .toci 0IN
O PRELIMINARY H 12ATION $0 ., REV DATE NEPARED BY- oATE G FinAt essex D .Y-- @s oars-v/e'e/sy REV_1_DATE 7/22/87 ,498 BOSTON ovo ,1 f#/ oA1, Mun WEDISON an,,,n cag
SUBJECT:
M-300 Cable Fire Heating of Torus Compartment Ceiling Beams SR h NSR ] wk, o .pg e A L4a.gS M ais=44 /== su/A O 0&uN{n # W ' g (IL/F) o 4e A - /4*y.d A @) O b & W Ngu, & h % e1.
~&hduuhus (e/t) ... O h e4. &
swk.(lb/f+) o w e & %f eev h & k sh d (B//b/F k - W). . The following values or expression are used for each of the tray section and beam combinations:
!s, = 65 Mle= l1,466 B/jf c,kt = p.II3 + 37If'ATw $b/F where the temperature-averaged specific heat expression is derived from the following values provided by Reference 14:
V qa= $./$7 d- $P
= p. h' 2 J H $ p P
g ,getygggy CALCULATION SHEET eggvuon o REV OATE PREFARED BY. CA.,E h
@ FINAL S $ _ DATE 2 N REV 1 DATE 7/22/87 Jh[8Q$7QM CHECKED y,yo ,r B]Ygf_ _pQy o r, WEDISON ,n,,,14 o,y
SUBJECT:
M-300 Cable Fire Heating of Torus Compartment Ceiling Beams Since the steel is initially assumed to be at 100F, and the SR h variation is assumed linear, NSR [ uf
- d R, C-,Q=$ $+ $(i .k. )+ '
Mg(/pB2WS}
- 2. //4W - 9 J
-l O , Eshd = Q.ll3 + 3 *l@# AT,,,. L
~
i Substituting these values into the expression for all tray / beam combinations, Ab = $5A%s /6. (gusv haObeec) 32no-32rrg d && hATlau,<guddh f s Q 31W%(sTwf+4,nsrArw = qs u r iy
)7W_ @!o%t+'KdX8v+%%%'-+ni;Q 1 sue-w --
(4wch k % L,sa u h >. % 4 l
%.e S 8 Ce PCN 8830
C PRELIMINARY H IZATioN No REV DATE PREPARED BY- oATE h,
@ FINAL CHF.CKED BY- oATE - N REV._1_DATE 7/22/87 ,((8Q$JQN ,,pv, ,v gjg om gg/p7 E!!!niVEDISON ,,,,,n ;36e
SUBJECT:
M-300 Cable Fire Heating of Torus Compartment Ceiling Beams t r SR h NSR l L I The maximum beam section temperatures determined by this i conservative analysis are all well below the critical failure temperature,of 1100F, The torus compartment ceiling beams are not subject to structural failure due to the burning of cables 1 in tray sections RP01 through RP07, even when considering the j impingement of the fire gas plume for cable fires located directly beneath the beams. l 1 Given that the cables are the only fixed combustible in the fire - area, the cables are located far from any exposure to possible ~l transient combustibles that may provide an exposure fire, the cables are all low voltage control cables, the cable combustible ! material is difficult to ignite and has passed the flame test
,' portion of the IEEE 383 standard, the cable tray sections are essertially horizontal raceways with only minor elevation changes over its run above the torus, and the torus compartment is a very large volume that can easily absorb the heat released by the fire both convectively and by radiation, it can be concluded that the integrity of the torus compartment ceiling is not threatened by a cable tray fire.
l l l l l 4 v l w o. ige e L Ce Na W
CALCULATION SHEET cyggz r C PREUMINARY REV DATE PREPAAED BY DATE-
@ FINAL CHECVEo RY DATE 7!Odl07 REV_1_DATE 7/22/87 SQ$7QN .,,vo ,v gg m,, fgg EDISON ,,,, n ,,g
SUBJECT:
H-300 Cable Fire Heating of Torus Compartment Ceiling Beams SR b NSR
6.0 REFERENCES
- 1. BECo LettFr No. 86-176, BECo Exemption Requests 11-14, November 14, 1986
- 2. BECo letter no. 87-062, 10CFR50, Appendix R Eremption Request-Supplemental Information on Tray Cover, April 21, 1987 ' '
- 3. Fire Protection Handbook, Fifteenth Edition, National Fire Protection Association, 1981
- 4. ASTM E119. "Standard Methods of Fire Tests of Building Construction
- 5. and Haterials," American Society for Testing and Naterials, Part 18.
Telephone Conversation with Mr. Ettore Bartolucci, Engineer with the Okonite Company, Ramsey, NJ, January 28, 1987
- 6. MalhotfA, H.L. , Detian o_f Fi re-Resi s tina Mruttuns-m Chapter 6 - Properties of Haterials, Chapter 9 - Design of Steel Elements, Surrey University Press, London, 1982 7.
Drawing no. C-132, Reactor Building Steel Framing Plan at Elevation 23 issue, 2/4/74 (see Attachment 4)f eet, Pilgrim Station, Unit 1, Boston Ediso B. 9. Okontte Product Data Sheets, Section 4, Sheet 3 (see Attachment 1) j Copper Conductor Tables (see Attachment 2) 4 10. Cablei Raceway Report, E345, Book 2, Pilgrim Nuclear Power Station, i Unit .h 11.
"Table of Properties for Designing H.H.S and HP Shapes, and Allowable Stress Design Selection", American Institute of Steel Construction, New York,1974, conforms to Supplement No. 3 to the AISC Specification, effective June 1,',1974 (See Attachment 6) 12.
Tewarson, A, Lee J.L. and Pion, R.F. ' Categorization of Cable Flammability Parameters," EPRI Report No. NP-1200, October 1979
- 13. Sundtra, "Categorization of Cable Flammability - Intermediate -
Scale Fire Tests of Cable Tray Installations," EPRI Report No. NP-1881 August 1982 [ 14. Table 1, Thermal Properties of Haterials SFPE, TR84-1, "Predicting Temperature Rise in Fire Protected Structural Steel Beams," Society of Fire Protection Engineers, 1984 (See Attachment 3) Jc. e ==
O PRELIMINARY CALCULATION SHEET igy,z,7,og go. nev oats % % " M "J ex raeaineo ev 2 o,1e W p X FINAL T&R 7j2kHeCKeo BY-- E DATe 7b 87 REV_1_DATE 7/22/87 g3[gQ$[Q$ ,y gg,, n ,, g/m WEDISON eues,n oeu
SUBJECT:
M-300 Cable Fire Heating of Torus Compartment Ceiling Beams l 1 SR b NSR j l 7.0 ATTACHHENTS
- 1. Okonite Product Data Sheets, Section 4, Sheet 3. (See Reference 8) ,
- 2. Copper Conductor Tables, (See Reference 9)
- 3. Table 1. Thermal Properties of Haterials, SFPE, TR84-1, (See Reference 14) .;
- 4. Copies of Portions of Marked-up Drawing No. C-132, (Reference 7) '
- 5. Figure 9.6, "Relationship between Ps/As and tf for unprotected stoel when Ts-550C ", (from Reference 4 )
e
- 6. Page 4 "H Shapes , Properties for designing", (From Reference 11)
- 7. Table 5-7, " Ratios of Heat of Combustion," (From Reference 12)
- 8. Table 5-1,"Radiative Heat Release Rates " (From Reference 13)
- 9. Table 5-2 "Convecti.ve Heat Release," (From Reference 13) l l
l l l l 1 e v i 1 l w . ,aci "
i
- / '
- m t D ata w
d' ._.. s.
,. . n . 4 : .S h.e.,et 3.,
s ., b numer Gm
- t. .sO. prene.
Mtrrer /ouwe mem.vece t-a .r7 - W. bbi - (smtware)
% G 13 tin 6 s pgyg ;j m gygfa
( W $ fdo cqasa % A
.. in,s. , , vsvvN
" C*onite ., , 3. i rwre for its NEC. .C::-uiid with flame and'nuis-heat res4stant, n . 4 rugged ture res,stant fulers where necessary em%ene.orooy noutanno and either an extruded toit or ceNe compound. The t no sic
- ness for tape.
wires saes #18 AWG th .@ #16 AM Gkl.w t is 25 mis; #14 AWG through #9 AWG is Overall Jacket Meets or me B ' requirements of IPCEA S 1941,5m
,30 mis. Conductors are paint co.or Edtion, Part 4. - "
coded wim solid and traosrr colors as required for proper ioentficanort Product Features
* *** ' #D Jacket Single Conductor ng Each single conductor has a 15 ml
. pie,jNe, easy to inmail and tirminde.
Choorene jacMt. The okoorov.e (neo-Color ceded. prene) jacMt assures circ.pt integnty
, gg g g g;; g g o ., , because of its l' ugh mechanical st ength, gg C' -
~
and excenent tescstance to flarm, ozone. of and most chem als. .
- RW sty at eie.ited terrceratures.
Overall Jacket . High insutabon thstancs, eton W The overan lacket is also Okoorene of e4evnted temperatures the prow Mness b me p D- 6teneter. The Okoprene (Neocrene) Additional inforrnation Jacket cssures circuit integnty because h Ms and Dmensens are of its Ngn mes.tumchi strengm and ex, Wred on de mm of tNs sheet, ce41ent resistance to flarre. or. ore, cil % in is ornented on ene n.mnem,, ==ste sheets fud in the teck ee E+ tNs seenon. For additional informabon
%g Applications contact vu iccal okenite rei.mera I tve or Sennce Cerver Manager Cl<oniteOcorene 600V 1000 control cables are recomrrended for use where maximum circuit integnty is recured se emil as ms;umum flame resastancA.
They are recommended for wet 9r dry nocenona. ac or a: sernce e conastor terrverstures to 90C. They met be ird staned in conoat, mets. case trougte a m tr m . j speciNetions NED CALC NO. bNdN/ ATTACHMENT I Con 6xtors Comed coom per Asw PAGE- I 1 sai or s.ies. cass s' Strand
- 0F ac s*. <-
o inwoosa . omae trehten: Meets or 'uceeds electncel N N $$2w"oN % e Joe w o******* 1 s ** and physcal roovirements of Intenm Standard si,IPCEA S48 516 (NEMA n a sw een or uwe t*** ene neers WC41971) aiid IPCEA S 1941,5th g s o *,, Jacw . otae vn* Edbon, Part 4 Paint cdor noded per hh d)U IPCEA S-1941, Port 5 Method I or per T l .'..
Product Data
. snite-O <oprene Section 4: Sheet 3 y Volt Control Cable Mo Copper Conductors /90C Rating mite-Insulation: P18 Awg & #16 Awg 25 rnils; 14 Awg through 9 Awg 30 ml:s: Single Ccc-idor Jadet 15 mH Omar JacAes aos Pee of peo.,g Thw*m Acaros O.D. MM eser Casert StreAWG Strones mes mm hh tri. mm th uar 11 1112 2 18 mLauw 7 45 1.14 .43 to 92 11 1113 3 18 107 121 7 45 1.14 .45 11 43 11 1114 4 123 139 18 7 45 1 14 12 44 49 148 11 1115 5 18 teh 7 60 1.52 .56 15.22 189 11 1117 7 18 219 7 60 1.52 .61 15.49 219 11 1119 9 262 18 7 60 1 S2 17 78 j 11 1122 .70 295 12 18 7 60 338 1.52 .00 20.32 355 11 1129 19 18 7 430 80 2 03 .92 23.36 449 11 1132 2 16 7 524 45 1.14 42 10 66 86 11 3133 3 16 7 96 45 1.14 44 11.17 97
)
11 1134 4 16 7 111 j 45 1 14 48 1219 120 11 1135 5 136 16 7 60 1.52 .56 11 1137 7 14.22 167 197 16 7 60 1.52 .61 11 1139 9 15 49 205 235 16 7 60 1 52 .70 17 78 295 334 11 1142 12 16 11 1149 7 60 1.52 .7f 20.06 324 399 - 19 16 7 80 2 03 .96 24.38 513 11 1152 2 14 7 821 45 1 14 .45 11 43 117 11 1153 3 131 14 7 45 1.14 .48 11 1154 4 12.19 125 141 14 7 60 1.14 .52 11 1155 5 13 20 168 196 14 7 60 1 52 60 1524 233 276 11 1157 7 14 7 60 1.52 .63 16 51 11 1159 9 14 255 296 7 60 1.52 .76 11.?162 12 14 19 30 344 419 7 60 2 03 90 2246 462 537 11 1169 19 14 7 80 2 03 1.04 26 41 662 11 1302 ~~I 12 7 45 1.14 .49 12 44 770 l 11 1303 3 141 157 12 7 60 1 14 .52 1 13 20 155 165 11 1304 4 12 7 60 1.52 .60 15.24 216 11 1305 5 12
- 7 244 60 1.52 .65 16.11 2 70 11 1307 7 12 7 313 60 1 52 .71 16 03 329 t 1 1309 9 12 7 372 ,
60 1.52 .82 20 82 445 11 1312 12 12 7 80 2,03 520 %
.97 24 63 000
't.1319 19 12 7 80 2 03 706 - 1.13 28 70 860 968 1 1482 2 10 7 60 1.14 11 1483 3 10 7 60 1.52
.54
.60 1422 15 24 188 218 b ;
i i.1464 236 266 4 to 7 60 1 52 65 16 Si 277 1 1485 5 320 10 7 60 1.52 .71 't.1487 18 03 347 390 7 10 Y 60 1.52 .77 g w LA. 11489 9 10 7 to 2 03 .95 19 55 24 13 442 664 Sir 739 g O 't.1492 % 12 10 7 80 2 03 1.06 26 92 784 892 1 1499 19 10 7 80 2 03 1.24 31.50 1147 11572 2 9 19 60 1292 fp 1.52 .59 14 to 11573 3 9 19 60 1.52 .63 16 00 226 294 256 337 gW Zh 11574 4 1 1575 5 9 9 19 19 to 60 1 52 1.52
.73
.75 18 54 it 05 325 417 See 457 b2 1 1577 115T9 9 7 9 9
19 19 80 1 52 .82 20 82 513 See h L4J 80 2 33 1.00 25 40 O 11582 12 9 19 e0 t us 1.12 775 843 O 11589 19 9 19 to 2.03 1.31 28 45 33 27 ess 1343 1041 1440 y4{ was tenweeem Qwentny for wesoct & Aymonted Stock iteq= Avedende Prom ewe t 20C2 esteet los tit & til Aug Cwasomer Service Centers i p C 10 000. , s
. ~ . . .e . ,m . . . , , a ,s.
. m .e .e ,. e~. ~e e..
~ ~~~ ,
e,1974 @ rse%oxodoR % % ome tNFORMATION ONIY
.sw ne ;ce wn dqF 80SRW CALCULATION COVER SHEET W ED/ SON PILGRIM NUCLEAR POWER STATION i'.%
g, _ ;a g
. CALC.NO. Nh REV. I File No. E SR h R. Type !
Subject LMW Fit?EkW/bs-6 TOEMS NSR l CDnipngrM1eXr/~ CE/uN6 8En(?IS l r DA V/h N EAMD in il n Discipline Approval /st GroupI/ ! %d Date 7/2z /p7 Due Date
~~
Pinsi Caic. ino pendent veritier MlticqcWktf dt/"aN 7/2 z/87 Statement Anac.ded g
-- num-sme summmmes Page(s) By kN h/d/6 Date C h'k'd f h, kf$f4W Date Agreed ISI c.
J tSI O. . YZ7.th Rummumme summmmmu hd ,/ul,j ha i I
$ l This design analysis ( ) DOES, Q>Q DOES NOT require revision to affected design documents.
n Documents: Affected A PDC ( ) IS, Desig%) IS NOT Required, A Safety Evaluation (
) IS, (K) 15 NOT Required Prior To Docurtynt Royle:orQMg SASA Group Leader ~iNmo%as I I . Tl v Cdncurred Date Minor revisions made on pages of this calculailon. See nort revlelon.
Replaces Cale. No. Vckled By Calc No. Or Attached Memo
% Exhlblt 3.05 B Rev. 4
CONDUCTOR TABLES COPPER l p - l 1 SOLID WIRE STRANDED CONDUCTOR-CLASS B l e strW conew y'g , 5 1 l 20 7 .8121 4 36 20 1.020 .0320 31 32 19 19 7 .0138 .042 1290 2353 39 4A 18 7 D152 045 18 1 820 0403 49_ - 50 16 7 D192 .057 16 2.540 0508 7.4 80 l 14 7 3242 AT2 14 4.110 D641 124 117 13 7 0272 080 tan h - f
.1019
_8Msi a 1 7 . 9 9 7 0432 .127 13.090 1144 39 6 40 4 g 8 16.510 .1285 . 50 0 y p,.86 .W SIA 6 6 7 2412 .179 I 26.240 .1820 79 4 80 9
*l)7T2 4 7 1
4 41.740 .2043 1260 226 * 129 0 3 7 0867 2 54 l 3 52620 2 294 159 0 162 0 .. ' 2 7 0974 245 2 66.360 .2576 201 0 2050 83690 1 19 0664 J24 2590 1 2893 2530 1/0 II A745 .363 1/0 105.600 J249 320 0 3260 2/0 133.100 2/0 19 A637 .404 411.0 3648 403 0 34 167.800 3/0 13 0940 4 58 514 0 , .4096 508 0 4/0 211.600 4600 641 0 AM 19 .1055 .514 653 0 2% 37 4822 341 7710 300 37 0900 414 925 0 350 37 D9T3 664 1.060 0 400 3F .1040 .710 1.234 0 t 4 50 37 1103 .753 1J90 0 .. 500 JI 37 .1162 .793 1.542.0 550 81 A950 .434 1.700 0 600 41 0992 871 1,450 0 650 41 .10J2 .906 2.006 0 700 61 .1071 .94 0 2.160 0 750 41 1109 9 73 2.316 0 600 41 .1145 1405 2.4690 650 81 .1160 1A35 2.6220 900 61 .1215 1 066 2.760 0 950 61 .1248 1 095 2.933 0 1000 61 .1280 1123 10840 1250 91 1172 1157 38590 1500 91 .12 H IJTT 46310 1750 127 .1174 1464 5.4030 2000 127 1255 1 591 61760 I
*22%
'2500 169 ill
.11 H
.1216 1 731 1A24 89650 )
F.794 0 1
*2750 21T 1126 1 914 LST20 I
'3000 217 .1176 1999 9.3490 i l
l N0tt 1 Cancas we m accata ce eth Astid 63. 68 833 w B189 h 0TI 2 SUWed ccrdct xs tNW 2000 uW w e Class I corvened strW e accensets ein ASTid 14 11, per 63
'h0TE 3 Cao.ctors tay than 2000 mand se Class C be ma corcentre.
NED cal.C NO. - dW
'2-ATTACHMEpT PAGE OF /
l 5 ' L SN 2.l c} 3(2I
,3,
*^
FOR INFORMAM . . . , . LY.. 1 kEOl47
i
.O l
i
? Table 1 Thermal Properties of hterials I '
kterial Thermal speciffe Heat Conductivity Density (8tu/1b 0F) (Ib/ft3) (Stu/f t hr 0F) Steel 30.0 0 00F 0.107 0 00F 480.0 24.7 9 6000F 0.144 0 7500F . - 20.1 0 11000F 0.172 911000F 15.0 0 20000F 0.172 0 20000F Fire Protection 0.034 0 00F 0.206 0 00F 15.0 - hterial 0.044 0 4000F 0.241 9 4000F 0.067 0 7500F 0.304 0 7500F Q 0.167 9 20000F 0.350 0 20000F Concrete 1 .01 9 00F 0.272 145.0 1.14 9 1600F 0.74 913000F ' '" 0.51 9 20000F . l O NED CALC NO. - ATTACHMENT N3 RM b PAGE- I 0F i O
,,, _ .1 y 2."2 #
- f. .e ...
. (( FOR INFORMRWANLY,,
i i k A Y74 f*lN A L'I $ 5 U E ,
~. h ' sis //C ]/4 f ', ,
'hh uv 5ED TYP.D"CLiNO f.LTOD5 LMn W U we f, f, F7/ N j
/S\ ISSOED. FOR NFORWK 104 WITH C .t& S.W. FJ .
~
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P ATTACHMENT 4
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1 I l 135 DESIGN OF FlRE RE5! STING STRUCTL*RES
- 80 I
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50-a
- I 40-e o 2
j 30- *g 20-1 10-i* O ^ i 50 ,) J. 100 150 Ps/As - lM' f Figure 9.6 Relationship betseen P 'A, and i for f uripeotected steel ahen T, = $5o*C. l l 1
- by the insulation to the f.ow of heat. If it is assumed that the rate of heat l
..l flow through the insulation results from a linear temperature gradient, the l
't l
quantity of heat received by the insulated section in time or is l 1 9= P,(Tf - 7,)or J/m (9.7) i d I/2 + ( 4 where x = coefficient of heat transfer (W/m 'C) 8
! J, = thickness ofinsulation (m)
A, = thermalconductisity ofinsulation (W/m'C)
?, - surface of the insulation facing the steel section (m8 /m)
Tf = fire temperature at time t ('C) l T, = steeltemperature at time t ('C) i or - time intersal. NED CALC NO. NM I0t/. l ATTACHMENT S PAGE / OF- / l N26 @ M
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4 0 W SHAPES
.,, Properties for designing 1
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l;tt ta.**2no. 1 S lr : I l S ; e l W i in.: y in. , an. en. e n.. en.e j in. e n.. l en. ] an.
*kg,h Mx300 88.3 M.72 16.655 1.640 ; 0.M5 1110 15.2 1300 156 3.83 l x280 !82.4 M.50'16.5M 1.570 0,885;19900 203001030 15.1 1200 144 3.81 x260 ' 76.5 I
M.24 ' 16.551' t.440 0.N1 17300 M2 15.0 ' 1090 ' 132 " 3.77 x245 72.1 ; 36 06' 16.512 1.350 ! 0.002' 16100 9M 15.0 1010 123 3.75 x230 l 67.7 ' 35.M 16.471 1.260 0.761 15000 637 14.9 940 114 3.73 W Mx1H 5?.2 M.44 12.117 ' t.260 0.770.12100 665 14.6 375 61.9 2.56 f x182 11300 622 14.5 MF 57.5 . 2.55 s jlM x170 53.6 50.0 l ' M.32 { 12.072 ; 1.100 0.7251320 M.16 12.027 { 1.100' O.600 [ 10600 500 14.5 $3.2 *2.53 ap x160 47.1 M 00 12.000 1.020 0.653 - 9760 542 14.4 2M 49.1 2.50 l
- - -' ' ' - - d'
-s g x150 x135 44.2 { 35.64 ;11.972 0.M0'0.625 9030 504 14.3 l 270 45.0 2.47 7420 I 440i14.0' 226 37.9 ' 2.39 W 33x240 39.8 l 35.55.11.M5
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70.6 l 33.50 15.065 1.400 0.830 ' 1M00 0.7Ml0.598
; I l 'l 813 ' 13.9 933 118 3.64 x220 ' 64.8 ' 33.25 15.810 1.275 0.775 12300 742 ~ 641 106 3.60 l ,{t3.h (t.M x200 54.9 ; 33.00! 15.750, 1.150; 0.715, 11100 671 ' 13.813.7M.2! 750 3.57 1 I l
, W 33x152 44.8 . 31.50 l 11.565 1.055 8160 0.635 447 ' 13.5! l273 47.2 i 2.47
.~ i x141 41.6 ' 33.31 11.535 0.960 0.605; 7460 , 444 ' 13.4 : 246 ! 42.7 l
, x130 6710 406 til '37.9{2.43 2.34 ag x118 34.3
- M.8 j 33.10 '11.510 0.155 0.54032.84 11.444 32.5 2.32 0.734 0.
g'h 30x210 61.9 30.34 15.105 1.315 0.771 9810 651 12.4 717 100 3.50 x190 54.0 30.12 15.040 1.185 0.710 8850 547 12.6 673 81.5 3.47 g (f,% x172 50.7 29.84 , 14.965 1.065 0.655 7910 $30 12.5 198 79.8 3.43 W 30x132 34.9 ' 30 30 10.551 1.000 0.615' $160 140 ; 12.2 i 196 37.2 2.25
e x124 g !M M.5 30.16 10.521'0.930 0.545 5MO 355 12.1 - lit H.4 2.23 8
iif x116 , 14.2 30.00' 10.500 0.850 0.564 e930 ' 329 12.0; 164 31.3 2.19
.g,, 6 x104 31.8 29.82 10.444 0.760 0.544 4470 300 11.9 146 27.9 2.15 ?
p px n ; 291 ;29.64 10.c4 0.670 0.m 40m l 2n 11.7 l 12 24.5 2.10 N+ Y 1 l Avtnican lastitutt or ststi, constnuction l NED CALC NO. MUM fdv. l ATTACHMENT fe PAGE I OF I
$ Mj3%
,,31,. 3 7 NED CALC NO. W N-[
ATTACHME T 9 unres er xtA: er Cerxes: Cx PAGE OF / Cable Sarple Hp/H g" HC "A
.H /P.n 'i (granularl 0.66 0.34 .
,'Y.'*.dPE (<iranularl
- 0.65 0.35
. 'idFE (82)
.63 0.37 A*
I I. , N 9; ' f ' r t. !a12) '; . 6 2 C.36
- yler. (nranular' # 0.61 0.39 ryC (granular) 0.59 0.41 1
XPE/rF).PZ (813) '.. 57 0.4? . - l l > Xi l'./C f ' .t ' Pt t e 15) " 57
. 0.43 )
TE/fvC (s4) e. 56 C.44 l e I xl E/!:reprene (s.1 '.53 0.47 ,, XPE/::ectrena (e17) 0,53 0.47 I E-::y/l "C-! ,- (s.6) ;.11 c.49 I l E/Pv; (e?) e ,9 ;,$1 1
- II/3M CI (granular)* 0.48 0.52 1
F E . !!y/T VC . !!y ( e l o) 0.48 0.52 H . It/Ci 'F' PF (e&) S.47 0.$3 l 9 IL/tvC (a)) . 41
. c.g9 XTE/XPE (814) !.40 0.60
, PL/ IVC (s'.) ?.37 0.63 ' 1 Pt. Pl /CI'F'PE (811) C.37 0.63
- 11. PI'/Cl's't r (810) 0.35 0.65 e-QTL/Ci'0*FE (816) 0.34 0.66 l
.411 cone, glass braid (8:1) 8.2% 0.71 I PL/46%Cl (granular)# 0.23 0.77 l
Filicone, glass braid /aebestos (8:2) 0.17 0.8) l Teflon (820) 0.13 0.08 l l
'It p Radiative Heat of Comhustier.: H g Actual Heat of Combustion li g Convective Hett of Coetustion
'peseatch samples ' data taken from Ref. (9)
I b T , A., LugL.3 J h. C*O l Smuks," em,R.E 'CMA j% Wt a pd u. DP-I244, 5-13 1 1
l 1 \ i Table 3-1 NED CALC NO. NW N f l ATTACHMENT F I noIATIvI HEAT RE:. EASE utis PAGE I OF - / !
= _ . . _ _ . . . . . . ..
N21'f N Cable Type Measured pediative Test and Maximum Relative Transmittance , Heat Release Id. Arrangement Radiation Humidity Coefficients Rate (kW) (t) (kW) { l I. TREE 8URi TESTS e 1 P/P-Ts 1198 38 0.850 1409 3 P/P-TS 2101 99 0.800 2626 4 P/P-ET 1604 74 0.821 1354 2 s/Al-Ts 708 57 0.799 886 . - 10 E/H-ET 186 84 0.816 228 9 i, 11 E/H-L 411 54 0.842 488 12 E/H-L3 1014 55 0.837 1211 , II EXTINGUISMMENT TESTS 5 P/P-ET 349 16 0.802 435 6 P/P-ET 507 70 0.820 618 7 P/P-tT 1503 76 0.815 1844 l 8 P/P-ET 2013 89 0.803 2507 I 9 S/A2-tT 74 86 0.795 93 1 # 13 E/H-LS 614 58
#Reu 1 0.839 732 14 E/H-Ls 250 75 g 0.825 303 , l l
III MIXED TRAYS - EXT!NCUISMMENT TESTS ! 15 P/P-ET 2218 35 0.884 2509 l 16 P/P-ET 1644 32 0.886 1856 17 P/P-ET 2213 76 0.800 2766 I l I l l l l 5-2 I I
O NED CALC NO. bD4 Nf
' ATTACHMENT Table 5-2 PAGE / OF- /
COtNECTIVE HEAT RELEASE $ Calculated values Relative Date of Cable Type Peak Peak Convective Test and Plume Plume Heat Zd. Arrangement Temp. Velocity Release *((M '
'C (20') m/see(ft/sec)
I razEaum nSTs 1 P/P-TS . 593 4.87(16.0) 2282 * ' 3 P/P-TS 628 5.25(17.2) 3334 4 P/P-ET 386 3.53(11.6) 1928 2 $/Al-TS 303 3.90(12.8) 1024 .,
# ~
10 E/H-ET 83 1.49( 4.9) 145 ! 11 t/H-L 99 1.53( 5.0) 61 - I {12 E/H-LS 230 3.10(10.2) 1427
!! EXTINGUISRMENT USTS I 5 P/P-ET 95 3.73(12.2) 612 ,
6 P/P-ET 159 3.32(10.9) 759 ** i 7 P/P-ET 193 2.79( 9.2) 1114 8 P/P-ET 311 4.80(15.7) 1665 l 9 S/A2-ET 25 1.04( 3.4) 80
~ l 13 E/H-LS 173 2.03( 6.7) 593 {
y 14 E/H-LS 83 1.25( 4.1) 181
*The value ' indicated in this colura is only an estimate of the actual < onvec.
tive heat release rate and is suitable for use in a relative study of fire intensity. It is not intended to be used in studies that require an exact value. i 1 1 i 5-3
l e Cale.ulation # N , Revision # has' been independently verified l by the following method (s), as noted belou: ) l
- Design Rcview _l including verification that:
- Design inputs were correctly selected and included in the calculation.
l -
- Assumptions are adequately described and are reasonable.
l
- Input or assumptions requiring confirmation are identified, and if any exist, the calculation has been identified as "Preliminary" and'a I
l "Finalization Due Date" has been spec V12d. . t Design requirements from applicable ndes, standards and regulatory documents are identified and refletted in the design.
- Applicable construction and operating experience was considered in the l design. !
- I l The calculation iumber has beer properly obtained and entered. , ,,
! I An appropriate design method or computer code was used. l
. A mathematical check has been performed.
. The output is reasonable compared to the input. l Alternate Calculation _ including verification of asterisked items noted above.
i The alternate calculation ( pages) is attached. l Qualification Testing _ for design feature including verification of asterisked items noted above and the following: ,
. The test was performed in accordance with written test procedures.
. Most adverse design conditions were used in the test.
. Scaling laws were established and verif.ied and error analyses were performed, if applicable. *
. Test acceptance criteria were clearly related to the design calculation.
Test results (documented in' ) werc reviewed by l the calculation Preparer or other cognizant engineer Independent Verifier Coments: M a.md hef _CswedwM OM Cows 8 WeM 4 hI Af a.c b . I ( , (9 See NED Procedure 3.05, Sec. 7.1.1 /s/ / d 7 2,/t ? Independenf VeF191er Date Preparer concurrence with findings and comment resolu- /s/ . m. tion Preparer or othe O 6 date cognizant engineer Exhibit 3.05-Q Rev. 8 l l 1 .__ _ . _ _ _ _ .. .
l l l socvurNr ; [0ELEASED JAh'4 g BOSTC,'t EDISON COMPANY N ;y q j, , PILGRIM "ATION '"# TELEPHONE CALLRECORQ TO: J. Keyes, S. Brennion, C. Hinott DATE: 12/16/87 TIME: 10:45 AH FRON: D. Nessman, Barry Marcus (NRC) and Allen Udi sEGG) !
SUBJECT:
BECo Response to Regulatory Guide 1.97 l This conference call was arranged by the NRC to re-visit where BECo and the NRC are with respect to Regulatcry Guide 1.97. Mr. Marcus is the NRC
%echnical reviewer and identified two areas to be addressed in the call.
- 1. Seismic Qualification, and
- 2. Inr:1vidual variables (independence) (Reference for phone call - BECo letter 87-021 dated February 10, 1987).
3.3.1 Seismic Oualificatient For seismic, BECo response indicated that we await the resolution of Generic Safety Issue A-46 by the NRC before any further action on our part. Mr. Udi stated that there is no reason to wait for A-46. If the i
' equipment in question meets the original FSAR design criterla then that is the answer the NRC will accept and Seismic Qualification is no longer an issue.
t Action: BECo to verify if original design criteria is met. 3.3.2 Neutron Flux BECo has adopted the BHROG position. Mr. Udi stated that the NRC has not accepted the BHROG position and would like BECo to commit to install CAT 1 wher, it becomes available on the market. He understands that G.E. now has a CAT 1 qualified system on the market and HNP-2 and Susquehanna have installed them. Mr. Marcus stated that he thinks the BHROG 1: developing a new position and if plants want to usa the BHROG generic position, then the BHROG needs to identify that it has the lead and start interfacing with the NRC. Action: None. BECo position remains the same. Copies To: S. Brennion J. Fulton C. Hinott J. D. Xeyes J. E. Howard R. N. Swanson P. T. Antonopoulos J. L. Rogers D. Varner S. Dasgupta R. E. Grazio R. V. Fairbank N D.Ild SIGNED CATE l Chrono File No: 2-0,7 Page 1 of l_ l j}}