ML093410541

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Calculation, DC00040-110, Revision 0, Post LOCA Sump Ph Effect from Miscellaneous Sources
ML093410541
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 11/25/2009
From:
South Carolina Electric & Gas Co
To:
Office of Nuclear Reactor Regulation
References
RC 09-0149 DC00040-110, Rev 0
Download: ML093410541 (38)
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Text

ES-0412 ATTACHMENT I PAG-E1-0F2 REVISION 5 Subject Code 004 SOUTH CAROLINA ELECTRIC AND GAS COMPANY CALCULATION RECORD Page 1 of 38 OPartial Calc. Revision

~Com Jete Calc. Revision Organization Date Worle Parsons 10/22/2009 XREF Number NA Calculation Title Post LOCA Sump pH Effect From Miscellaneous Sources Parent Document System ECR 71072 NA Originator Discipline M. Waselus AE Calculation Number DC00040-110 Safety Class ONN OQR

~SR Revision o

Status CALCULATION INFORMATION Content

Description:

The purpose of this calculation is to evaluate the effects of the sources listed in NUREG/CR~5950 on the post LOCA sump pH to assure the sump pH is maintained above a value of

7. Maintaining the sump pH greater than 7.0 post-LOCA precludes the need to consider iodine reevolution from the sump during the LOCA in calculating the potential offsite and control room radiological consequences.

Affected Components/Calculations/Documents:

NA Piping Reconciliation Completed per QA-CAR-0089-18: OThis Revision 0 Previous Revision

~ N/A Contains Preliminary Data/Assumptions: ~ No 0 Yes, Affected Pages:

Computer Program Used:

~ No o Yes, Validated per computer program validation process (others) vendors name o Yes~ Validated in accordance with SAP-1040/ES-413 (ref. 3.4 & 3.5) o Yes, Validated [ES-0412]

o Computer Program Validation Calculation VERIFICATION 0

Continued, Attachment Scope:

The scope of this review/verification is to confirm that the calculation is complete and accurate and in accordance with ES-412 requirements.

~~

1(j/lG-~1 En ineerin Personnel/Date t&1tJJ Verifier/Date A

RECORDS To Records Mgmt:

"~"":::---

Initialsfljate

SOUTH CAROLINA ELECTRIC & GAS COMPANY REVISION

SUMMARY

Calculation Number DC00040-110 ES-0412 ATTACHMENT I PAGE 2 OF 2 REVISION 5 Page 2 of 38 Revision Number.

o Summary Description Initial Issue

DC00040-110 Revision 0 page 3 of38 TABLE OF CONTENTS RESULTS 26 PURPOSE 4

METHOD 7

REFERENCES 27 Hydriodic Acid 8

Nitric Acid 10 Hydrochloric Acid 12 Sodium Hydroxide 18 Cesium Hydroxide 20 Summary of Acid and Base Production.........................*............................................................. 22 Boric Acid 7

DESIGN INPUT 5

ASSUMPTIONS 5

COMPUTER CODE 5

1.0 2.0 3.0 4.0 5.0 5.1 5.2 5.3 5.4 5.5 5.6 5.7 6.0 7.0 Cable Data per TWR Serial 66006 (attached) 28

DC00040-110 Revision 0 page 4 of38 1.0 PURPOSE The purpose ofthis calculation is to evaluate the effects ofthe sources listed below on the post LOCA sump pH to assure the sump pH is maintained above a value of 7 (Reference 1). Maintaining the sump pH greater than 7.0 post-LOCA precludes the need to consider iodine reevolution from the sump during the LOCA in calculating the potential offsite and control room radiological consequences. This calculation is based on the methodology provided in NUREG/CR-5950 (Reference 2), NUREG-1081 (Reference 3) and NUREG/CR-5732 (Reference 4). This calculation supplements calculation DC00040-066 (Reference 5) which determines a conservative (with respect to reevolution of iodine) post LOCA pH exclusive ofthe additional sources addressed herein. Per NUREG/CR-5950 there are a variety ofacids and bases produced in containment during a LOCA. These include the following:

Boric acid is a weak acid and will enter containment from accumulators, refueling water storage tanks, sprays, and the reactor coolant system (RCS).

Hydriodic Acid (HI) is a strong acid introduced into containment with the release of iodine.

Carbon Dioxide (C02) which depresses the pH ofwater by being absorbed in water from air to form carbonic acid. Carbonic acid is a weak acid the effects ofwhich are insignificant relative to the other acids produced during the LOCA.

Nitric acid (RN03) is a strong acid produced by the irradiation ofwater and air.

Hydrochloric acid (HCl) is a strong acid produced by the radiolysis or pyrolysis ofchlorine bearing materials during the accident. Per section 2.2.5.3 ofNUREG/CR-5950, pyrolysis occurs at temperatures around 752 OF which is well above the post LOCA temperatures (maximum containment temperature < 330 OF). Therefore, only radiolysis is considered in this analysis.

Sodium Hydroxide (NaOH) is a strong base introduced as the primary buffer into containment via the reactor building sprays.

Cesium Hydroxide (CsOH) is a strong base introduced into containment with the release of cesium during the accident.

Core-Concrete Aerosols are basic materials released from the interaction ofthe molten core materials with concrete. Consistent with the course ofthe postulated accident, core damage is assumed to be terminated after the in-vessel release phase and these chemicals are not considered any further herein.

DC00040-110 Revision 0 page 5 of38 2.0 COMPUTER CODE No software other than Microsoft EXCEL was used in this calculation. EXCEL was used for numerical manipulation.

3.0 ASSUMPTIONS The following assumptions are used in this analysis:

The beta dose to cables is reduced by a factor of 2 due to localized shielding effects.

The gaseous HCI produced by cable radiolysis will be conservatively assumed to be instantly dissolved in the sump.

The sump is taken as well mixed by action ofthe ECCS systems such that a single pH value can be applied to the entire sump.

4.0 DESIGN INPUT The following design input data is used in this analysis:

1.

Minimum sump pH per DC00040-066 = 7.5. Section 4.0 [page 20] DC00040-066 provides a brief description ofthe operating conditions for the 4 cases. In all cases, the pH is ~ 7.5. The pH ranges from a low of7.5 in the sump at the end ofthe injection phase to a high of8.8 during the injection phase, and is 8.0 at sump equilibrium after the SHST is empty.

2.

Weight percent of chlorine for the various cable insulations (Attachment 1).

3.

Post LOCA Gamma and Beta dose rate profiles and integrated doses in the reactor building atmosphere and sump are taken from the Equipment Qualification database. In accordance with USNRC RG 1.183, section 1.3.5 and SECY-98-154, the TID-14844 Equipment Qualification dose rates previously calculated in the containment air and sump (beta and gamma) bound those generated by AST. The reactor building EQ zones are shown on Reference 9. The 30 day reactor building doses are taken References 9 and 10.

RB Doses (f4 T = 30 days Dose (Rad)

Dose (Mrad)

Airborne gamma 2.2+07 22 Airborne beta 1.4+08 140

DC00040-110 Revision 0 page 6 of38 4.

Conservative values for the core inventory of cesium and core inventory ofiodine in gram moles.

These inventories include the stable Cs-133 and 1-127 species. The values are provided via References 8 and 13 and reproduced below.

Inventory Inventory (gram Nuclide (2rams) atoms)

Nuclide (2rams)

(2ram atoms) 1-127 3.71E+03 2.92E+01 Cs-133 8.39E+04 6.31E+02 1-128 2.52E-02 1.97E-04 Cs-134 1.87E+04 1.40E+02 1-129 1.53E+04 1.19E+02 Cs-134m 8.52E-01 6.35E-03 1-130 1.27E+00 9.77E-03 Cs-135 3.19E+04 2.36E+02 I-130m 1.10E-02 8.45E-05 Cs-135m 2.18E-03 1.61E-05 1-131 6.63E+02 5.06E+00 Cs-136 9.08E+01 6.68E-01 1-132 1.15E+Ol 8.71E-02 Cs-137 1.08E+05 7.89E+02 1-133 1.47E+02 1.11E+00 Cs-138 3.33E+00 2.42E-02 I-133m 6.19E-04 4.65E-06 Cs-138m 1.70E-02 1.23E-04 1-134 6.70E+00 5.00E-02 Cs-139 9.61E-01 6.91E-03 I-134m 4.99E-02 3.72E-04 Cs-140 1.01E-01 7.19E-04 1-135 4.37E+01 3.24E-01 Cs-141 2.88E-02 2.04E-04 1-136 6.81E-02 5.01E-04 Cs-142 1.14E-03 8.02E-06 I-136m 2.44E-02 1.79E-04 Cs-143 5.63E-04 3.96E-06 1-137 1.99E-02 1.45E-04 Cs-144 9.54E-05 6.65E-07 1-138 2.58E-03 1.87E-05 Cs-145 1.43E-05 9.83E-08 1-139 4.45E-04 3.20E-06 Cs-146 7.29E-07 4.99E-09 1-140 4.63E-05 3.31E-07 Cs-147 4.71E-07 3.20E-09 1-141 3.74E-06 2.65E-08 Cs-148 1.15E-08 7.80E-l1 1-142 3.10E-07 2.19E-09 Cs-149 O.OOE+OO O.OOE+OO 1-143 3.70E-08 2.59E-10 Cs-150 7.14E-12 4.76E-14 1-144 1.33E-09 9.23E-12 1-145 O.OOE+OO O.OOE+OO Total 1.99E+04 1.55E+02 2.43E+05 1.80E+03

5. Minimum post-LOCA sump volume (55730 fe or 1.578E+6Iiters) per Reference 11.

DC00040-110 Revision 0 page 7 of38 5.0 METHOD 5.1 Boric Acid Per Reference 5, page 77, for the minimum pH design case mass boric acid = 58245 Ibm Boric acid does not dissociate in aqueous solution, but is acidic due to its interaction with water molecules to form the tetrahydroxyborate ion:

B(OH)3 + H20

~

B(OH)4 + H+ (Ka = 5.8xlO-lO mol/l; pKa = 9.24)

Converting to gm-moles results:

58245 Ibm B(OHh

  • 453.59 gm/lbm I 1 mole I 61.82 gm I 1.578E06liters = 2.708E-Ol moles/liter or a total of 427320 moles [2.708E-Olmoles/liter
  • 1.578E6 liters].

based on minimum sump LOCA volume per Section 4, Item 5.

DC00040-110 Revision 0 page 8 of38 5.2 Hydriodic Acid Per section 2.2.2 of Reference 2, hydriodic Acid (HI) is a strong acid introduced into containment with the release of iodine, but small amounts are likely in containment.

Table 2 of USNRC Regulatory Guide 1.183 (Reference 1) indicates that 5% of the halogen inventory is released during the gap release phase and an additional 35% is released during the early in-vessel phase.

In accordance with Section 3.5 of Reference 5, 95% ofthe iodine released should be assumed to be cesium iodide (CsI) 4.85% elemental and 0.15% organic iodine. The basis for this release was NUREG-1465, section 3.5 (Reference 7) wherein it states iodine entering containment is at least 95% CsI with the remaining 5% as I plus HI, with not less than 1% ofeach as I and HI. This analysis will conservatively assume that all 5% ofthe release is in the form ofHI in order to maximize the acid generation. This release process is assumed to occur at a constant rate over the release period identified in Table 4 of Reference 1.

LOCA Release Phases PWRs Reference 1 Phase Onset Duration Gap Release Early In-Vessel Release 30 sec 0.5 hr 0.5 hr 1.3 hr The core iodine inventory used in this evaluation includes stable I127 to maximize the amount ofacid produced. Per Reference 13 the total core inventory of iodine is 155 gram atoms at the end of cycle.

Note: For a monotonic element gram mole equals gram atom. The following equations are used to describe this release.

During the Gap Release Phase:

d/dt[HI] = [0.05

  • 0.05 mi] / [Vs
  • 0.5 hr]

During the Early In-Vessel Release Phase:

d/dt[HI] = [0.05

  • 0.35 mi] / [Vs
  • 1.3 hr]

where:

mi = gram mole iodine = 155

DC00040-110 Revision 0 page 9 of38 Vs Sump volume = 1.578E+061iters (minimum sump LOCA volume per Section 4, Item 5.)

Integrating the above yields:

During the Gap Release Phase:

[HI](t) = [mil / [.5 / (.05*.05)]Vs * [t-tgrp]

[HI](t) = [mil / [200Vs] * [t - tgrp]

where tgrp = onset of the gap release phase = 0.008333 hr [0.5 minutes or 30 seconds]

During the Early In-Vessel Release Phase:

[HI](t) = [mil / [1.3 / (.05*.35)] Vs] * [t -(0.5 + tgrp)] + [0.5 mil / [(200Vs]

[HI](t) = [mil / [74 Vs] * [t -(0.5 + tgrp)] + [mil / [400 Vs]

The final HI concentration at t = 1.808 hr [1.3 hr+0.5hr+30 seconds], the end of the iodine release from the core is given as:

[HI](1.808 hr) = [(155) / (74*1.578E+06)] * [1.808 -(0.5 + 0.008333)]

+ [155] / [400*1.578+06]

[HI](1.808 hr) = [1.3274-06] *[1.3] + 2.4556-07 = 1.9712-06moles/liter or a total of 3.1 moles [1.9712-06 moles/liter

  • 1.578+06 liters].

DC00040-110 Revision 0 page 10 of38 5.3 Nitric Acid Radiolytic production of nitric acid is discussed in section 2.2.4 ofReference 2 and section 3.3.1.1 of Reference 4. The nitric acid (RN03) is produced by the irradiation of water and air. Both references provide the following constant for nitric acid production based on experimental data: g(RN03) = 0.007 molecules/1 OOev where the relationship is based on radiation absorption in the aqueous phase. This value is based on a water temperature of 86 of, which is conservative for use following a LOCA since the solubility ofnitrogen reduces with increasing temperatures. Per Reference 2 section 2.2.4, this equates to a radiation G value of7.3-06 moles RN03/ L Megarad which means H+ and N03increase by 7.3-06 moles/L for each Megarad ofdosedelivered to the sump water. This is expressed as:

d/dt[RN03] = 7.3-06 moles RN03/ L Megarad

  • DR(t) where: DR(t) = dose rate as a function oftime in the sump (Megarads/hr).

For the purposes of determining the quantity of nitric acid formed, a 30 day sump integrated dose of40 Mrad is applied based on Table 5-8, "Integrated Gamma Ray and Beta Source Strengths at Various Times Following a Maximum Credible Accident (TID-14844 release fractions)" ofReference 12.

T 5-8 RADM 30 day Conservative Integrated y/~ MEV/Watt Source Strength at Time After Energy Group Release Power (2958 MWt)

MeV/gamma MeV/Watt Watt MEV Mrad (1) 0.20 - 0.40 2.30E+14 2.96E+09 6.80E+23 0.40 - 0.90 2.70E+14 2.96E+09 7.99E+23 0.90 - 1.35 5.40E+13 2.96E+09 1.60E+23 1.35 - 1.80 7.20E+13 2.96E+09 2.13E+23 1.80 - 2.20 1.60E+13 2.96E+09 4.73E+22 2.20 - 2.60 1.70E+13 2.96E+09 5.03E+22 2.60 - 3.00 1.50E+12 2.96E+09 4.44E+21 3.00 - 4.00 8.50E+11 2.96E+09 2.51E+21 4.00 - 5.00 2.10E+ll 2.96E+09 6.21E+20 5.00 - 6.00 1.10E+10 2.96E+09 3.25E+19

DC00040-110 Revision 0 page 11 of38 Total 'Y 6.62E+14 2.96E+09 1.96E+24 19.84 Beta 6.60E+14 2.96E+09 1.95E+24 19.79

'Y = [1.96E+24 Mev]

  • 1 erg/6.25E5 Mev
  • 1 Mrad/106 Rad *1 cc/gm = 19.84 Mrad 1.578E09 cc Beta = [1.95E+24 Mev]
  • 1 erg/6.25E5 Mev
  • 1 Mrad/l06 Rad *1 cc/gm = 19.79 Mrad 1.578E09 cc These dose rates were determined using TID-14844 source terms. In accordance with USNRC RG 1.183, section 1.3.5 and SECY-98-154, the TID-14844 Equipment Qualification dose rates previously calculated in the containment air and sump (beta and gamma) bound those generated by AST. Therefore, it can be concluded that the dose rates calculated with TID-14844 are conservative and acceptable for use in determining the HN03 production herein.

[HN03](t) = 7.3E-06 It DR(t) dt where t = time into accident (hrs) or the nitric acid produced at any point in time is given as

[HN03](t) = 7.3E-06

  • Integrated Dose at Time 1.

[HN03](30 days-sump dose) = 7.3E-06

  • 40 = 2.92E-04 moles/liter.

or a total of 460.8 moles [2.92E-04 moles/liter

  • 1.578E6 liters].

DC00040-110 Revision 0 page 12 of38 5.4 Hydrochloric Acid The radiolysis ofchloride-bearing cable jacketing will result in the production ofHCI vapor as documented in Section 2.2.5.2 ofNUREG/CR-5950 (Reference 2). It should be noted that a significant portion ofthe HCI vapor produced from cable radiolysis would react with the metal components within the primary containment (e.g., cable trays, gratings, etc.) and never enter the sump. However, for this analysis it is conservatively assumed that all ofthe gaseous HCI produced is immediately dissolved in the sump water. A model for the production ofHCI from cable jacketing is developed below based on the approach given in Appendix B ofNUREG/CR-5950.

The absorption ofa radiation flux at a radius, r, can be described from basic principles as:

q> (r) = q> (Ro)e-1l(Ro-r)

!..L = Linear Absorption Coefficient (em-I) from Table below.

Ro = Outside cable radius (em)

Cable and Air Material Properties Reference 3 Density Linear Absorption Coefficient (em-I)

Material (gm/cm3)

Beta Radiation Gamma Radiation Hypalon 1.55 52.08 0.099 EPR 1.27 42.67 0.081 Air 0.0198 0.0000374 Similar to the approach in Reference 2, Appendix B, the production ofHCI from radiolysis is given by:

R= G (SA) q> A where:

R = HCI production rate (gm moles/sec)

G = Radiation G value for Hypalon (molecules HClIl 00 ev)

SA = Cable surface area (cm2) q> = Incident radiation energy flux (Mev/cm2-sec)

A = Absorption fraction ofenergy flux in Hypalonjacket.

Radiation G value for Hypalon

DC00040-110 Revision 0 page 13 of38 Note: The radiation G value for Hypalon adopted in Reference 2, Section 2.2.5.2 is 2.115 molecules HCI per 100 eV. This G value is based on the energy absorbed by the polymer consistent with the footnote to Table 3 ofNUREG-1081 (Reference 3). As described in Reference 3, this value represents a balance between the increased HCI production at elevated temperatures expected during accidents and the neutralization potential offillers in the cable. The resulting value is 3.512E-20 moles/Mev (Reference 2, page B.3). This term can also be expressed in terms ofmoles/Mrad (absorbed dose)-gm (exposed material).

3.512E-20 moles/Mev

  • 6.25E+5 Mev/erg
  • 100 ergs/gm-Rad
  • 1E+6 Rad/Mrad = 2.195E-6 moles/Mrad-gm or 9.97E-4 moles/Mrad-lb. This value is conservative compared to the value of 4.6E-4 moles ofHCI per Ib of insulation per Megarad listed in Section 2.2.5.2 of Reference 2 since it produces about 2.2 times more HCI per lb of exposed material.

Absorption fraction of energy flux in Hypalon jacket The absorption fraction is the fraction of incident radiation energy flux absorbed by the Hypalon. As provided in Section 4.2 ofNUREG-1 081 (Reference 3), the factor is calculated with the following equation (Reference 3, Equation 4 gamma and Equation 4 beta):

Ay,H = 1 - exp[-Ill

  • tH]

where:

Ay,H = Absorption of incident gamma radiation III = Linear adsorption coefficient - gamma Hypalon (0.099/cm) tH = Hypalon thickness (em)

Ap,H = 1 - exp[-1l~H

  • tH]

where:

Ap,H = Absorption ofincident beta radiation Il~H = Linear adsorption coefficient - beta Hypalon (52.08/cm) tH = Hypalon thickness (em)

Using the above equations and values the following figure plots the radiation fluxes through Hypalon jacketing. As seen essentially all ofthe beta energy is completely absorbed even by relatively thin

DC00040-110 Revision 0 page 14 of38 Hypalon cable jacketing while very little ofthe gamma energy is absorbed. In the subsequent analysis all ofthe beta energy will be assumed completely absorbed in the jacket.

1.2000 1.0000*

~

u:::

gamma 0.8000 s::::

(1)

't:l'0

.5 0.6000 0

s::::

0

~

0.4000 0

C'll...

U.

0.2000 0.0000 -

0 0.02 0.04 0.06 0.08 0.1 0.12 Cable Thickness (inches)

Hel Generation The HCl generation can be calculated with the above equations as (See Reference 3, Equations 5-7 and 5-8 for gamma_and Equations 5-10 and 5-11 for beta).

Gamma: R = G (SA)

>)/ ~yair] * [1-exp (_~yH*tH)] Beta: R = G (SA) <p A = G

  • E~N
  • 1/~~air where:

R EyN E~N ~yH ~yair r ~~air HCl production rate (gram moles/hr) Energy release rate / unit volume (Mev/hr-cc) gamma Energy release rate / unit volume (Mev/hr-cc) beta Linear adsorption coefficient - gamma Hypalon Linear adsorption coefficient - gamma air Distance ofair to cable (cm) (252 cm). Linear adsorption coefficient - beta air SA tH G Cable surface area (cm2) Hypalon thickness (em) 3.512E-20 gram moles/Mev (Reference 1, Appendix B) DC00040-110 Revision 0 page 15 of38 Using the form for G in terms of absorbed dose [9.97E-4 moles/Mrad-lb (exposed material)], the total HCl generation from an integrated energy release is given as follows: Gamma: MHCl Beta: MHcl where: MHCl W t [1-exp(-f.lfH*tH)] fat DR dt G = G

  • W* * [1-exp(-f.lfH*tH)]fot DR dt

= G

  • w* fat DR dt HCl production (gram moles)

Weight of cable jacket material (lbs) Time (hrs) Fraction of gamma energy absorbed Integrated dose (Mrad) moles/Mrad-lb Using G in terms of absorbed dose (Mrad) replaces G (EyN) [(1-exp( _f.lyair*r)/ f.lyair] where the values were in terms of an incident flux and absorbed energy. Due to the different attenuation properties of beta and gamma radiation they are addressed separately. Beta: From Attachment 1, the total weight of cable jacket (17083 lb) and insulation (36540 lb) (assumed to be Hypalon properties) is taken as 63812lbs [(17083 + 36540)

  • 1.19]. Also as seen on above figure and on, the jacket thickness in almost all cases is equal to or greater than the thickness required for the entire beta energy to be absorbed, therefore, use ofthe total jacket + insulation is conservative.

The Hel concentration in the sump is MHcl / Sump Volume (1.578E+6liters) or [HCl] = G

  • W* Integrated Beta Dose

DC00040-110 Revision 0 page 16 of38 [HCl] = 9.97E-4 moles/Mrad-lb

  • 63812lbs
  • 12[140 Mrad] / 1.578E+6liters

[Hel] = 2.8222E-03 moles/l due to beta or a total of 4453.4 moles [2.695E-03 moles/liter

  • 1.578E6 liters].

where a factor of 2 reduction is taken for the beta dose due to self shielding effects. Gamma: Unlike beta radiation, the gamma radiation can penetrate the cable interior and HCl may be generated by interior jackets on individual conductors in multi conductor cables. Based on a review ofthe various cable types listed in Attachment 1, a bounding cable type is developed to conservatively determine the potential HCl production. A review of Attachment 1 indicates that type EK-BIG and EK-CIA cables comprise about 13.14% and 27.95% of the total cable length and 14.05% and 14.84% ofthe total outside jacket mass, respectively. Based on this type EK-CIA is used as the base for the subsequent evaluation. Per Reference 14 for type EK-CIA cable the OD = 0.436 in. where the properties for Hypalon are conservatively applied to the EPDM insulation material. The resulting EK-CIA insulation-jacket mass/ft is conservatively applied to the total length for all cable types from. DC00040-110 Revision 0 page 17 of38 Approximate Representation of Cable OR= 0.218 in 0.045 in Hypalon jacket Outside radius = 0.0255 + ~~--+--t---- 0.015 + 0.03 = 0.0705 inches 0.0255 in radius conductor 0.01 5 in Hypalon primary jacket 0.03 in EPDM primary insulation There are two 16 gage conductors with 30 mils EPDM and 15 mils Hypalon each. Per Marks (Reference 6), diameter of 16 AWG conductor equals 51 mils or 0.051 inches (radius = 0.0255 inches. Therefore, the area of insulation-jacket/conductor is: rc[R/ - R]2] = rc[(0.0705in/12in/ft)2 - (0.0255in/12in/ft)2] = rc[0.0000345 -.0000045] = 9.425E-5 ft2/conductor The total mass ofinsulation-jacket is conservatively estimated as: 2 conductors

  • 9.425E-5ft2/conductor
  • 96.7 lb/ft3
  • 289,914 ft = 5285 lbs.

Where: 96.7 lb/ft3 = density of Hypalon 289,914 ft = total length ofall cable from Attachment 1. By inspection of Attachment 1, type Q11 cable bounds most types of cable used and provides a conservative estimate ofthe material used to generate HCl. HCl concentration in the sump is MHcl / Sump Volume [HCl] = G

  • w* * [1-exp(-~fH*tH)]
  • Integrated Gamma Dose

[Hel] = 9.97E-4 moles/Mrad-lb * [63812 + 5285]lbs * [(1 - exp- (.099

  • 0.436)] * [22 Mrad] /

1.5788E+6 liters [HCl] = 9.97E-4

  • 69097 lbs
  • 0.0422
  • 22 /1.578E+6

[HCI] = 4.053E-5 moles/liter due to gamma or a total of 64 moles [4.053E-5 moles/liter

  • 1.578E6 liters].

Therefore, the total gamma + beta HCI equals 64 moles + 4453.4 moles =4517.4 moles. DC00040-110 Revision 0 page 18 of38 5.5 Sodium Hydroxide In order to maintain the post LOCA sump pH greater than 7 a buffering agent is required to offset the various acid production post LOCA. NaOH solution is used (NaOH). The molecular weight is: Component No. ofAtoms Atomic Weight Na 1 22.9898 H 1 1.00794 0 1 15.99994 Total 40 gm/mole Per Reference 5, page 77, for the minimum pH design case mass NaOH = 3829.046 Ibm Converting to gm-moles results: 3829.046 Ibm NaOH* 453.59 gm/lbm / 1 mole / 40 gm / 1.578E06 liters = 2.7516E-02 moles/liter or a total of 43420 moles [2.7516E-02 moles/liter

  • 1.578E6liters].

Sodium hydroxide (NaOH), also known as lye and caustic soda, is a caustic metallic base. Sodium hydroxide forms a strong alkaline solution when dissolved in a solvent such as water. However, only the hydroxide ion is basic. Sodium hydroxide dissociates in water as follows: NaOH + H20 --. Na + OH + H20 Therefore, the injection of3829.046 Ibm NaOH or 43420 gm-moles NaOH results in 43420 gm-moles basic OH. Base will buffer the sump water at a pH corresponding to the following: pH = pKa + log [anion]/[acid] (Henderson-Hasselbalch equation per page 754 ofReference 15) where: = negative ofthe log ofthe acid dissociation constant = -log[Ka] Per Reference 2, section 2.3.3, a borate buffer that controls pH at values near 9.2 has a dissociation constant of 5.8E-l 0 and a phosphate buffer that controls pH at values near 7 has a dissociation constant of 6.3E-08. Sodium hydroxide is a strong base that controls pH at values near 11. The value of 5.8E-l0 from Reference 2, section 2.3.3 is conservatively assumed in this analysis for NaOH buffering. [anion] [acid] where: 5.8E-IO = for borate buffer (Reference 2) = borate concentration = acid concentration DC00040-110 Revision 0 page 19 of38 pH = pKa + log [anion]/[acid] DC00040-110 Revision 0 page 20 of38 5.6 Cesium Hydroxide Per section 2.3.1 of Reference 2, cesium may be introduced into containment in various forms following an accident. The cesium will form cesium hydroxide and cesium borates which are basic materials Table 2 of USNRC Regulatory Guide 1.183 (Reference 1) indicates that 5% ofthe alkali metal inventory (including cesium) is released during the gap release phase and an additional 25% is released during the early in-vessel phase. Table 2 Reference 1 also indicates that 5% ofthe halogen inventory is released during the gap release phase and an additional 35% is released during the early in-vessel phase. In accordance with Section 3.5 of Reference 1, 95% ofthe iodine released should be assumed to be cesium iodide (CsI). This release process is assumed to occur at a constant rate over the release period identified in Table 4 of Reference 1. LOCA Release Phases PWRs Reference 1 Phase Gap Release Early In-Vessel Release Onset 30 sec 0.5 hr Duration 0.5 hr 1.3 hr The core cesium and iodine inventories used in this evaluation include stable Cs-133 and stable 1-127. Per References 8 and 13, the total core inventory ofiodine is 155 gram atoms at the end of cycle (EOC) and the total core inventory of cesium is 1800 gram atoms at EOC. Note: For a monotonic element gram mole equals gram atom. The following equations are used to describe this release. During the Gap Release Phase: d/dt[CsOH] = [0.05mcs - (0.95

  • 0.05mi)] / [Vs
  • 0.5 hr]

During the Early In-Vessel Release Phase: d/dt[CsOH] = [0.25mcs - (0.95

  • 0.35mi)] / [Vs
  • 1.3 hr]

where mi = gram mole iodine = 155 mcs = gram mole cesium = 1800 Vs = Sump volume (liters) = 1.578E+061iters [55730 ft3] DC00040-110 Revision 0 page 21 of38 Integrating the above yields: During the Gap Release Phase: [CsOH](t) = {[(.05/.5)mcs - (.05*.95/.5)mi] / [Vs]) * [t - tgrp] [CsOH](t)= {[0.lmcs-0.095mi]/[Vs]} * [t-tgrp] where tgrp = onset ofthe gap release phase = 0.008 hr [0.5 minutes or 30 seconds] During the Early In-Vessel Release Phase: [CsOH](t) = {[(0.25/1.3)mcs - (.35*.95/1.3)mi] / [Vs]) * [t -(0.5 + tgrp)] + [(0.1 *.5)mcs-(0.095*.5)mi] / [Vs] [CsOH](t) = {[0.19mcs - 0.256mi] / [Vs] * [t -(0.5 + tgrp)]} + [0.05mcs - 0.0475mi] / [Vs] The final CsOH concentration at t = 1.808 hr [1.3 hr+0.5 hr+0.008 hr] is given as: [CsOH](1.808 hr) = {[0.19

  • 1800 - 0.256
  • 155] / [1.578E+06]} * [1.808 -(0.5 + 0.008)] + [0.05
  • 1800 - 0.0475
  • 155] / [1.578E+06]

[CsOH](1.808 hr) = ((342 - 39.7]/[1.578E+06)) * [1.3] + [90 -7.4]/ [1.578E+06] [CsOH](1.808 hr) = [2.49E-04] + [5.23E-05] moles/liter [CsOH](1.808 hr) = 3.013E-04 moles/liter or a total of 475.5 moles [3.013E-04 moles/liter

  • 1.578E6 liters].

DC00040-110 Revision 0 page 22 of38 5.7 Summary of Acid and Base Production The following provides a summary ofthe production of acids and bases in the sump for 2958 MWt Material Concentration in Concentration in Sump Concentration Reference Sump generated generated by gamma in Sump Section by Beta radiation radiation moles/liter moles/liter moles/liter Boric Acid 2.71E-01 5.1 Hydriodic Acid NA NA 1.97E-06 5.2 Nitric Acid NC NC 2.92E-04 5.3 Hydrochloric Acid 2.82E-3 4.05E-5 2.86E-03 5.4 Sodium Hydroxide NA NA 2.75E-02 5.5 Cesium Hydroxide NA NA 3.01E-4 5.6 NA: Not Applicable NC: Not Calculated Material Sump gm-moles Reference Section Boric Acid 427320 5.1 Hydriodic Acid 3.1 5.2 Nitric Acid 460.8 5.3 Hydrochloric Acid 4517.4 5.4 Total acid 432301.3 Sodium Hydroxide 43420 5.5 Cesium Hydroxide 475.5 5.6 Total Base 43895.5 Base Case pH considering only boric acid and sodium hydroxide = 8.244 (No credit for CsOH production): Hydriodic Acid O.OOOE+OO Nitric Acid O.OOOE+OO Hvdrochloric Acid O.OOOE+OO Boric Acid 2.708E-01 Total Acid 2.708E-01 Cesium Hydroxide O.OOOE+OO Sodium Hvdroxide 2.752E-02 Total Base 2.752E-02 pH=pKa+loQ[total base/total acid] Ka pKa pH 5.800E-10 9.237E+OO 8.244E+OO where pKa = -log[Ka] DC00040-110 Revision 0 page 23 of38 Base Case pH considering only boric acid and sodium hydroxide = 8.248 (With credit for CsOH production): Hydriodic Acid O.OOOE+OO Nitric Acid O.OOOE+OO Hydrochloric Acid O.OOOE+OO Boric Acid 2.708E-01 Total Acid 2.708E-01 Cesium Hydroxide 3.010E-04 Sodium Hvdroxide 2.752E-02 Total Base 2.782E-02 pH=pKa+loq[total base/total acidl Ka pKa pH 5.800E-10 9.237E+OO 8.248E+OO DC00040-110 Revision 0 page 24 of38 Additional Cases with no credit for CsOH production: Hydriodic Acid O.OOOE+OO Hydriodic Acid 1.971 E-06 Nitric Acid 2.920E-04 Nitric Acid O.OOOE+OO Hydrochloric Acid 2.860E-03 Hydrochloric Acid 2.860E-03 Boric Acid 2.708E-01 Boric Acid 2.708E-01 Total Acid 2.740E-01 Total Acid 2.737E-01 Cesium Hydroxide O.OOOE+OO Cesium Hydroxide O.OOOE+OO Sodium Hydroxide 2.752E-02 Sodium Hvdroxide 2.752E-02 Total Base 2.752E-02 Total Base 2.752E-02 pH=pKa+loQ[total base/total acid] Ka pKa pH pH=pKa+loQ[total base/total acid] Ka pKa pH 5.800E-10 9.237E+OO 8.239E+OO 5.800E-10 9.237E+OO 8.239E+OO Hydriodic Acid 1.971 E-06 Hydriodic Acid 1.971 E-06 Nitric Acid 2.920E-04 Nitric Acid 2.920E-04 Hydrochloric Acid O.OOOE+OO Hydrochloric Acid 2.860E-03 Boric Acid 2.708E-01 Boric Acid 2.708E-01 Total Acid 2.711 E-01 Total Acid 2.740E-01 Cesium Hydroxide O.OOOE+OO Cesium Hydroxide O.OOOE+OO Sodium Hydroxide 2.752E-02 Sodium Hydroxide 2.752E-02 Total Base 2.752E-02 Total Base 2.752E-02 pH=pKa+loQ[total base/total acid] Ka pKa pH pH=pKa+log[total base/total acid] Ka pKa pH 5.800E-10 9.237E+OO 8.243E+OO 5.800E-10 9.237E+OO 8.239E+OO Hydriodic Acid O.OOOE+OO Hydriodic Acid O.OOOE+OO Nitric Acid O.OOOE+OO Nitric Acid O.OOOE+OO Hydrochloric Acid O.OOOE+OO Hydrochloric Acid 2.860E-03 Boric Acid 2.708E-01 Boric Acid 2.708E-01 Total Acid 2.708E-01 Total Acid 2.737E-01 Cesium Hydroxide O.OOOE+OO Cesium Hvdroxide O.OOOE+OO Sodium Hydroxide 2.752E-02 Sodium Hydroxide 2.752E-02 Total Base 2.752E-02 Total Base 2.752E-02 pH=pKa+loQ[total base/total acid] Ka pKa pH pH=pKa+loQ[total base/total acid] Ka pKa pH 5.800E-10 9.237E+OO 8.244E+OO 5.800E-10 9.237E+OO 8.239E+OO Additional Cases with credit for CsOH production: DC00040-110 Revision 0 page 25 of38 Hydriodic Acid O.OOOE+OO Hydriodic Acid 1.971E-06 Nitric Acid 2.920E-04 Nitric Acid O.OOOE+OO Hydrochloric Acid 2.860E-03 Hydrochloric Acid 2.860E-03 Boric Acid 2.708E-01 Boric Acid 2.708E-01 Total Acid 2.740E-01 Total Acid 2.737E-01 OH-for pH = 7.5 3.160E-07 OH-for pH = 7.5 3.160E-07 Cesium Hydroxide 3.010E-04 Cesium Hydroxide 3.010E-04 Sodium Hydroxide 2.752E-02 Sodium Hydroxide 2.752E-02 Total Base 2.782E-02 Total Base 2.782E-02 pH=pKa+log[total base/total acid] Ka pKa pH pH=pKa+log[total base/total acid] Ka pKa pH 5.800E-10 9.237E+OO 8.243E+OO 5.800E-10 9.237E+OO 8.244E+OO Hydriodic Acid 1.971E-06 Hydriodic Acid 1.971 E-06 Nitric Acid 2.920E-04 Nitric Acid 2.920E-04 Hydrochloric Acid O.OOOE+OO Hydrochloric Acid 2.860E-03 Boric Acid 2.708E-01 Boric Acid 2.708E-01 Total Acid 2.711 E-01 Total Acid 2.740E-01 OH-for pH = 7.5 3.160E-07 OH-for pH = 7.5 3.160E-07 Cesium Hydroxide 3.010E-04 Cesium Hydroxide 3.010E-04 Sodium Hydroxide 2.752E-02 Sodium Hydroxide 2.752E-02 Total Base 2.782E-02 Total Base 2.782E-02 pH=pKa+log[total base/total acid] Ka pKa pH pH=pKa+log[total base/total acid] Ka pKa pH 5.800E-10 9.237E+OO 8.248E+OO 5.800E-10 9.237E+OO 8.243E+OO Hydriodic Acid O.OOOE+OO Hydriodic Acid O.OOOE+OO Nitric Acid O.OOOE+OO Nitric Acid O.OOOE+OO Hydrochloric Acid O.OOOE+OO Hydrochloric Acid 2.860E-03 Boric Acid 2.708E-01 Boric Acid 2.708E-01 Total Acid 2.708E-01 Total Acid 2.737E-01 OH-for pH = 7.5

3. 160E-07 OH-for pH = 7.5 3.160E-07 Cesium Hydroxide 3.010E-04 Cesium Hydroxide 3.010E-04 Sodium Hydroxide 2.752E-02 Sodium Hydroxide 2.752E-02 Total Base 2.782E-02 Total Base 2.782E-02 pH=pKa+log[total base/total acid]

Ka pKa pH pH=pKa+log[total base/total acid] Ka pKa pH 5.800E-10 9.237E+OO 8.248E+OO 5.800E-10 9.237E+OO 8.244E+OO DC00040-110 Revision 0 page 26 of38 6.0 RESULTS The results ofthe evaluation based on the above data are summarized as follows: Case pHNoCsOH pHwith CsOH Base Case Boric Acid & NaOH only 8.244 8.248 All 8.238 8.243 All - Nitric Acid 8.239 8.244 All-HI 8.238 8.243 All-HCI 8.243 8.248 HClonly 8.239 8.244 The results herein indicate that the prior pH prediction provided in Reference 5 are conservative from a minimum pH perspective i.e. 8.2 versus 7.5. Nevertheless, as demonstrated in this calculation the effects of the additional acids: Hydriodic Acid (HI), Nitric acid (HN03)and Hydrochloric acid (HCl) have a negligible effect ofthe post LOCA sump pH <<0.1). Therefore, the conclusion that the post LOCA sump pH remains above 7, thereby precluding iodine re-evolution pH as previously identified in Reference 5 remains valid. DC00040-110 Revision 0 page 27 of38

7.0 REFERENCES

1.

USNRC Regulatory Guide 1.183, Alternative Radiological Source Terms For Evaluating Design Basis Accidents At Nuclear Power Reactors, July 2000.

2.

NUREG/CR-5950, Iodine Evolution and pH Control, Revision 3 (12/92).

3.

NUREG-I081, Post-Accident Gas Generation from Radiolysis of Organic Materials, September, 1984.

4.

NUREG/CR-5732, Iodine Chemical Forms in LWR Severe Accidents, April, 1992.

5.

Calculation DC00040-066, Spray and Sump pH With Delta-75 SGs, Revision 1.

6.

Marks Standard Handbook for Mechanical Engineers, i h edition.

7.

NUREG-1465, Accident Source Terms for Light-Water Nuclear Power Plants-Final Report, February, 1995.

8.

Westinghouse Letter to Wayne Stuart (SCE&G) Core Inventories ofIodine and Cesium Isotopes at End-of-Cycle for V. C. Summer, CGE-09-27 dated July 23,2009.

9.

VCS Drawing SS-021-009, Revision 1.

10. VCS Drawing S-021-018, Sheets 3-185 and 3-192.
11. Calculation DCOI380-002, Sump Volume, Revision 3.
12. Westinghouse Radiation Analysis Manual, Revision 1 for VCSNS Uprating updated 12/98 (attachment to letter CGE-98-036).
13. Westinghouse memo, Core Inventories ofIodine and Cesium Isotopes at End-of-Cycle for V. C.

Summer, LTR-REA-09-116 dated July 23,2009.

14. TWR Serial 66006, Determination of Chlorine Containing Cables within Reactor Building, 7/26/2009 (Attachment 1).
15. Ebbing and Gammon, General Chemistry, 7th edition, Houghton Mifflin Company (2002)

Cable Data per TWR Serial 66006 (attached)

DC00040-110 Revision 0 page 28 of38

Page

-I of 6

Project Title Objective:

ENGINEERS TECHNICAL WORK RECORD Determination of Chlorine containing Tab Cables within Reactor Building.

Serial:

Engineer:

Date:

66006

l. Budo DC00040-110 Revision 0 page 29 008 TIlis n\\TR relates to EIR-81550. The purpose of this 1V\\IR is to describe and discuss the methods used to determine cables located within the RBand the Chloride presence in the insulation of these cables.

Step 1 Objective:

TIle objective of Step 1, designed and executed by Donn Kelly, \\vas to deteulline the tyl)es, quantities, and overall insulation weights of Cables found \\\\'ithin the RB. This infol111ation was fInalized in the Excel output of "qry - LIST Step B-Cable by BOM KnO\\vn to be in RB". A second list of Cables, named "qlY - LIST Step D - Cable by BOM in ullktlO\\Vn locations", was generated in order to identif:y the cables with unktlown locations.

A series of PCCKS Access output tables \\vere used as source clata tables in order to identify the locations of cables and further determine those being within the RB.

These tables, \\:vhich are shown belmv, were grouped in a single Access database named "Tables on PCCKS-VCS_Tables 2009-07-21".

A second Access database, named 'CablesInRB Rev 04' \\vas created to analyze the input data obtained from PCCKS. The process of identifying and S01ting cables vdthlll the RB, III order to deteulline their types and total lengths for use in Step 2. is Sho\\:I;11 as a list of consecutive queries below', TIle ftmction of each query is explallled below.

Step 1 ",vas reviewed by Ilir Budo..

The logic desclibed below ensures that, based on data availal)le, all knO\\\\'n cables located within the RB are captured and considered.

Tables on PCCKS-VCS Tables 2009-07-21 BOM01AOO.

CIROIAOO, CONOIBOO,
CON02AOO, CON03AOO,
SSA01AOO, TRi\\01AOO.

TRAOIBOO, TRAOICOO, TRA02AOO, TRA02BOO Queries l)"qry - step 101 - Append valid circuits" appends hue values from Fields CIR_NMfE, GR_TYPE, CIR_BOM, and CIR_CLENGTH fl:om table CIROIAOO (direct product of PCCKS) to table <Cables in RE' 2)"qlY - Step 103 - IvIark Cableslll Tray in RB" updates Fields CktInRB and CktInTrayRB of table 'Cables III RB' with tme values v{henjoin conditions are met.

3)"qry - Step 104 - Mark Cables in Tray Outside" updates Fields CktOutRB and CktInTrayOut when join conditions are met

Page 2

of 6

Project Title ENGINEERS TECHNICAL WORK RECORD Determination of Chlorine containing Tab Cables within Reactor Building.

Serial:

Engineer:

Date:

66006

l. Budo DC00040-110 Revision 0 page 30 of38 4)"qry-Step105 -

Mark Cables in RB in Conduit" updates Fields CktInRB and CkInCondIl1RB with true values when Join conditions are met 5)"qry - Step 106 - Mark Cables in Conduit Outside" updates Fields CktOutRB and CktInCondOut oftable 'Cables in RB' when join conditions are met.

6)"qlY - Step 207 - Mark Cables in RB based on FT tag" updates Field CktInRB and FromOrToInRB oftable 'Cables in RB' \\vhenjoin conditions are met.

7)"qlY - Step 208 - Mark Cables based 011 FT tag Outside" updates Fields CktOutRB and FromOrToOut of table 'Cables in RB l' and confhms that the circuits are out RB when join conditions are met.

8)"qry - Step 209 - Mark Cables in RB based on RBPen" updates Fields CktInRB and RBPenInRB of table 'Cables in RB_1' and conti.nus that circuits are in RB \\vhen join conditions are met.

9)"qlY - Step 2lO - Mark Cables based onRBPen Outside" updates Fields CktOutRB and RBPenOut oftable 'Cables in RB_l' whenjolll conditions are met.

lO)"qry -

Step 219

- l'vfark in RB from Gel1Data" updates Fields CktInRB and FromOrTobyGenDataInRB of table 'Cables III RB' \\vhen all join conditions are met.

11)"qlY - Step 220 - Mark Outside RB from Gel1Data" updates Fields CktOutRB and FromOrtoByGenDataOut when all join conditions are met.

l2)"qlY - Step 30I-List From and To Boxes" pOltrays data lUlder Fields CIR_NA."!\\1E, Ck.iInRB and CktOutRB, from table 'Cables III RB' and data from Fields CIR_ESYST, CIR F DESC and CIR T DESC from table CIROIAOO and Fields FromBox and ToBox when the join conditions are met.

13) "qlY - Step 302 - List From and To boxes clean fonnat" updates new Field,;; FBox and TBox.

14)"qry - Step 305 - Match boxes to locations" looks lllto Tables TellllBoxData and "qlY-Step 302" and creates and shows clata for tlu'ee new fields CIR_NAME, FBox, and ToBox 15)"qlY - Step 307 - Deime box location table" defInes box locations by looking into Step 305

DC00040-110 Revision 0 Page 3

of 6

Project Title ENGINEERS TECHNICAL WORK RECORD Determination of Chlorine containing Tab Gables within Reactor Buifding.

Serial:

Engineer:

Date:

66006 L Budo July 261\\

2009

16) "qry - Step 309 - IvIark Inside based 011 box locations" updates Fields CktInRB and BoxlnRB fi'om table 'Cables in RB' \\vhenjoin conditions are met.
17) "qlY - Step 310 - Mark Outside based on box locations" updates Fields CktOutRB and BoxOutside :11"01n table 'Cables in RB' when join conditions are met.
18) "qlY - Step 3.51 - List From and To Paging" updates data for the new FromSpkr, ToSpkr, and FromHalld Fields, by looking into Tables 'Cables in RB' and CIR01AOO, \\vhen join conditions are met.
19) "qlY - Step 352 - 'Valid Speaker circuits" shows valid speaker circuits from Step 351.
20) "qry - Step 353 - Find Speakers in RB" fmds Speaker Circuits in RB by fmding Speakers in RB, looking into step 352 and table 'ReactorBldg_H3ndSet-Speaker_Data'
21) "qlY - Step 354 - Find Speakers Outside RB" created by s!lm,'illg Fields from Step 352 22)"qIY-step 355 - Mark speakers in RB " updates Fields CktInRB and PageIllRB from Table 'Cables in RB' \\Vhel1 join conditions bet\\veen Step 353 and table 'Cables in RB' are met.
23) "qlY - Step 356 - :Mark speakers outside RB" updates Fields CktOutRB and PageOutside ii'om table 'Cables in RB' when Join conditions bet\\veen table List Speakers outside RB and table Cables in R.B are met.
24) "qry - Step 372 - Valid Handset circuits" looks into Step 351 and shows valid Handset Circuits.
25) "qry - Step 373 - Find Handsets in RB" finds valid Handset circuits from Step 372 that are-located within the RE.
26) "qlY - Step 374 - Find Handsets Outside RB" shows Handset Circuits outside RB by looking into Step 372 and table Reactol'Bld_Handset-Speaker_Data.
27) "qlY - Step 375 - J\\.1:ark handsets inRB" updates Fields CKlnRB and PagelnRB from table

'Cables in RB' when join conditions bet\\veen step 375 and table 'Cables inRB' are met.

Page 4

of 6

Project Title ENGINEERS TECHNICAL WORK RECORD Determination of Chlorine containing Tab Cables within Reactor Building.

Serial:

Engineer:

Date:

DC00040-110 Revision 0 page 32 of38 66006

l. Budo July 26th, 2009
28) "qlY - Step 376 - Mark handsets outside RB" updates Fields CkiOutRB and PageOutside
l}0111 Cables in RB when join conditions bet\\veen tables 'List handsets outside RB' and

'Cables in RB' are met.

29) "qlY - Step 411 - Mark in RB by Area Field" updates Fields CktInRBand ArealnRB fi:om table 'Cables in RB' whenjoin conditions 'Nith table Cir01AOO are met.
30) "qlY - Step 412 - 1V1ark by Area Field Outside" updates Field,:> CktOutRB and AreaOutside from table 'Cables ill RB' whenjoinconditions lith table Cil'OIAOO are met
31) "qlY - Step 514 - Mark Outside based on system" updates Fields CktOutRB and SysOutsicle fi'om table 'Cables in RB' \\vhenjoin conditions are met
32) TIle following 'VB code was developed in order to determine the location of those pmticular circuits \\vith unclear locations.

TIle fol1mving Sql Strings select those particular circuits that have not been idelltitled and flagged to this point as being Inside Ol" Outside the RB:

SqlStr =

"SELECT CIR01AOO.CIR_NAlvIE, CIROIAOO.ClR_F_DESC, ClR01AOO.CIR_T_DESC, {fbI -

Cables in RBI CktOutRB, [fbI - Cables in RB].D"'1ScOutside "

SqL5tr = SqIStr &: "FROM{tbi - Cables.in RB] IJ.lJvER JOIN" Sq1Str = SqIStr &: "CIR01AOO ON ({fbI - Cables in RBj.CIR_TYPE = CIROIAOO.CIR]YPE) A.ND ([fbi -

Cables in RB].CIR_JI1.A..?i1E = C1ROIAOO.G'IR_NA.J.l1E)"

SqlStr

=

SqlStT "WHERE

(((Itbl

(,nbles in RB].CktOutRB)=No) jL\\i]) (([tbl

- Cables in RB].CktInRB)=No)j;"

i\\nd SqlStr =

"SELECT CIROIAOO.CIR_NA..A1E, CIROIAOO.ClR F DESC, ClROIAOO.CIR_T_DESC, {fbI -

Cables in RB].CktlnRB, [fbl-C,ables in RB].DescInside 11 SqlStr = SqlStr &: "FROM[tbI - Cables.in RB] 1J.llVER J01J.l" Sq1S'tr = SqlStr &: "CIR01AOO ON ({fbI - Cables in RB].C1R_TI'PE = CIR01AOO.G'lR_HPE) AND ([fbi -

Cables in RB]. CIR_JVA..J.1E = C1ROIAOO.C'IR_NAJ.l1E)"

SqlStr =

SqIStr "WHERE

((([tbl -

(,nbles

.in RB].Cl.-tOutRB)=1Vo) A.,\\i]) (([tb1 Cables in RB].ClrtlnRB)=No)); "

Flu*thennol'e, the following 'If InStr' ftmctiolls "vere used to determine the location of the records produced by the SqlStrs sho\\;vn above by comparing string words and phrases-known to be inside or outside the RB against the 'From' and 'To' description recorclsets.

StInSt = RslnSt("lnsideString" IfInStr(l, StF_DESC, StInSt,):> 0 OrlnStr(l, StT_DESC, StlnS!,)::> 0 Then RsCi7s.Edit RsCJ..::ts("CktlnRB") = Tme

Page 5

of 6

Project Title ENGINEERS TECHNICAL WORK RECORD Determination of Chlorine containing Tab Cables within Reactor Building.

RsC-7f:t.s(/tDesdnside':) = True Serial:

Engineer:

Date:

DC00040-110 Revision 0 page 33 of38 66006

!. Budo July 26th, 2009 And StOlttSt = RsOlttSt("OutsideString'~

IfInStr(l, StF_DES'C, StOutSt) > 0 Or InStr{1, StT_DESC, StOutSt) >. 0 Then RsCkts.Edit RsCkts(YfCktOutRB'? = Tnte RsCkt.s("DescOutside'?= True The "]nside8tring" is (C'RDM INST PLUG; CRDM PLUG BOARD; CRDM PWR PLUG; LEG; AT]

DETECTOR; PRESSfIRlZER; PRZR; RCS; RRd.CTOR BLDG & REACTOR Bl/IWING)

The "OutsideString" is (ATWS l\\.fITlGATJON 81'S ACT C.ilB; Ar.lX BLDG; AlJX BLR; Al.lXBOlLER; C".4BLE STORAGE;' C'A.lvfER.4... CARDOX' CH...4.RGIJ:lG CABLES:' CHILLER AREA.; cmJPRESSOR.;

CmvlPUTER RlvE; CO'l.tfPDTER ROOiW,: CO!VllEN:SIlvTG LIN/T; CONT BLDG; CONT R.\\1; CONT. ROD LOGIC e4B; CONTROL BLDG; CONTROL ROOM; COOLfl'>lG TOTVER; CPTR R.t.\\£; CPTR ROOM; DELUGE;' DOloJESl1C,' DOOR A; DOOR C; DOOR F; DOOR I; DOOR S:' E FlELD; E-FIELD; FILT "VATER; FIRE PROT COlvY; FIRE SERV; FIRE SERVICE; FOR CB; HALON; HYDRO PLAJI/T;

!NDlISTRL4L; L"vTERMED BLDG; LSO PHASE; ISOPHASE; L4B; L4.U:NDRY Rom...t; 1'-'£4111/

DISTRIBl.lTION FRAJJ,fE; M4...?\\'HOLE~* MCB TERlvf PANEL,' MCC; lvflCROW:4VE; MOBILE HIBE,'

MOlvTI(-:ELLO,' MUCLEAR OP5:' OFFICE,' OPERA.TIONS BLDG; OPERA.TIONS BUILDING; PARR HYDRO; POTABLE WATER; RAD 1l1ADlT BLDG,' RECORDS ROO].,!,' SEClJ.RlTY BLDG; SECURITY ENGR BLDG; SERV BLDG; SERVICE BLDG; SHOP; STOR BLDG:; TOOL ROo.~1; TRAINING; TURB BLDG; TURB. BLDB.; WAREH07:]SE &ZOlvE)

33) "qry - LIST Step B - Cable by BOM Known to be in RB" updates Fields BOr'll ill, Cable Desc, Total Length. and Total Insulation \\-Veight obtained in "qry-LIST Step A-Qty Cable K110\\Vn to be in RB" by looking into tables 'Cables inRB', CIROIAOO. alldBOMOlAOO.
34) "qlY - LIST Step D - Cable by BOM in unktl0\\Vn locations" updates Fields BOI\\i1 ID, Cable Desc, Total Length, and Total Insulation "'7eight obtained in "qlY - LIST Step C -

Qty Cable f01' ullkno\\vn locations" by looking into tables Cables in RB, CIROlAOO and B01.VfOlAOO.

Step 2 Objective:

The clata obtained :fl:om Step 1 was further analyzed by Ilir Buclo. BOM records, PCCKS BOM Infonnation repOlt # CKSR0350 and archived EQDPs of vmious cable vendors "vere used to detemline the Chlorine content of the insulation and jacketing of evelY type of cable identitled as being \\vitbin the RB or ofunknown location.

Page 6

of 6

Project Title ENGINEERS TECHNICAL WORK RECORD Determination of Chlorine containing Tab Cables within Reactor Building_

Serial:

Engineer:

Date:

DC00040-110 Revision 0 page 34 008 66006 I. Budo Excel tables, exported from step one Access database 'CableslnRB Rev 04', 'LIST Step D -

Cable by BONI in UnknO\\vn Locations', and 'LIST Step B - Cable by BaNI Known to be in RB' were combined in one Excel me ealled 'List B+D Updated July 23rd FIN...t\\L.xls'. There \\vere 5 new colunms added to the 'Final B List' and 'Final D List': Vendor, GAl SPEC, Chlorine Content, Data fOlUld, and Data Sou,ree columns. All relevant data is stored under column 'Data Found'. Cohlllm'Chlorine Content' identifies aU BONI ill entries as 'Yes'-containing Chlorine,

'No'-not containing Chlorine, and '1' for all entries for \\vhich it was not possible to dete11lllne Chlorine content based on available vendor supplied histOllcal data.

FOl' cables located inside the RB the total weight of insulation of cables vdth unknown Chlorine content is 3.7% of the total weight of insulation of all cables located inside the RB. For cables with UnblO\\\\TI location, the total \\veight of insulation of cables \\\\'ith UnbI0\\\\'!1 Chlorine content is 3.,5%) of the total weight of the insulation of all cables,,vith unkno\\vll location..

'Notes and Observations' sheet of 'List B+D Updated July 23rd FINAL.xIs' file shows a SUn111lalY of data described above.

FurthelTIlOre, a ue"" sheet named 'Calc' was created ill order to systematically tabulate all the necessary data needed to calculate the Chloride weight against the individual BOlvls.

DC00040-110 Revision 0 page 35 of38 File "Calc" per TWRSerial66006 (Reference 14) Known Cables in the Reactor Building CALCULATED VALUES NUMBER OF Hypalon 1.55g/cc mH SA SA Total wt

%wt Sum Of Total Insulation Outside Outside Jacket Cable Code Length(ft)

Chlorine Content Weight(lb)

Diameter (inch)

CONDUCTORS CONDSIZE Thickness OR inch OR-OJT density Ib/ft sq cm/ft sq cmllb jacket Ibs CFC-13 2259

?

16 0.190 4

24 0.025 0.095 0.07 96.7 8.70E-03 46.2118 5310.242 19.66 0.07 CFC-30 3161

?

506 0.863 10 16 0.065 0.4315 0.3665 96.7 1.09E-01 209.8990 1918.135 345.90 1.59 CFC-48 5275

?

58 0.300 4

22 0.050 0.15 0.1 96.7 2.64E-02 72.9660 2766.916 139.11 0.37 CFC-61 2625

?

407 0.667 8

16 0.065 0.3335 0.2685 96.7 8.26E-02 162.2278 1965.173 216.70 1.16 CFC-71 250 Yes 49 0.585 COAX 0.065 0.2925 0.2275 96.7 7.13E-02 142.2838 1995.372 17.83 0.12 EK-A1A 358 Yes 1751 3.740 3

750 0.140 1.87 1.73 96.7 1.06E+00 909.6434 855.511 380.65 3.98 EK-A2G 797 Yes 1060 2.260 3

350 0.110 1.13 1.02 96.7 4.99E-01 549.6776 1101.697 397.65 2.72 EK-A2H 1470 Yes 1712 2.000 3

250 0.110 1

0.89 96.7 4.39E-01 486.4403 1109.073 644.74 4.39 EK-A2J 744 Yes 734 1.800 3

4/0 0.095 0.9 0.805 96.7 3.42E-01 437.7963 1281.177 254.24 1.84 EK-A2M 2014 Yes 1406 1.430 3

1/0 0.095 0.715 0.62 96.7 2.68E-01 347.8048 1299.918 538.86 3.63 EK-A2S 220 Yes 95 1.220 2

1/0 0.080 0.61 0.53 96.7 1.92E-01 296.7286 1542.232 42.33 0.26 EK-A38 139 Yes 47 0.820 2

6 0.065 0.41 0.345 96.7 1.04E-01 199.4405 1926.364 14.39 0.11 EK-A3C 375 Yes 98 0.740 2

8 0.065 0.37 0.305 96.7 9.26E-02 179.9829 1944.461 34.71 0.25 EK-A3D 4326 Yes 908 0.610 2

10 0.065 0.305 0.24 96.7 7.47E-02 148.3643 1985.202 323.30 2.30 EK-A3E 2906 Yes 1212 1.610 3

2 0.080 0.805 0.725 96.7 2.58E-01 391.5845 1516.454 750.40 3.66 EK-A3F 1195 Yes 541 1.020 3

4 0.080 0.51 0.43 96.7 1.59E-01 248.0846 1563.749 189.58 1.36 EK-A3G 2283 Yes 895 0.870 3

6 0.065 0.435 0.37 96.7 1.10E-01 211.6015 1916.879 252.02 2.14 EK-A3H 122 Yes 46 0.790 3

8 0.065 0.395 0.33 96.7 9.94E-02 192.1439 1932.682 12.13 0.11 EK -A3J 8157 Yes 1175 0.640 3

10 0.065 0.32 0.255 96.7 7.88E-02 155.6609 1974.165 643.17 3.39 EK-A3K 136 Yes 88 1.270 4

2 0.085 0.635 0.55 96.7 2.12E-01 308.8896 1453.621 28.90 0.22 EK-A3P 2367 Yes 1053 1.210 3

1 0.080 0.605 0.525 96.7 1.91 E-01 294.2964 1543.127 451.42 2.81 EK-81F 120 Yes 8

0.380 1

12 0.050 0.19 0.14 96.7 3.48E-02 92.4237 2655.121 4.18 0.02

>? iF

>>Vh';>

Fi 2>>

>'*i>

12 F

                  • .*.**'i.

"i ii iiii ii vz.

'i

'Hh Fi EK-81H 6146 Yes 1039 0.640 3

12 0.065 0.32 0.255 96.7 7.88E-02 155.6609 1974.165 484.61 2.84 EK -81J 9207 Yes 1722 0.690 4

12 0.065 0.345 0.28 96.7 8.57E-02 167.8219 1958.125 789.09 4.68 EK-81K 5971 Yes 1254 0.740 5

12 0.065 0.37 0.305 96.7 9.26E-02 179.9829 1944.461 552.69 3.37 EK-81L 4285 Yes 1016 0.800 7

12 0.065 0.4 0.335 96.7 1.01 E-01 194.5761 1930.519 431.88 2.70 EK-81M 4011 Yes 1384 1.060 10 12 0.080 0.53 0.45 96.7 1.65E-01 257.8134 1558.743 663.41 3.82 EK-81N 815 Yes 347 1.190 15 12 0.080 0.595 0.515 96.7 1.87E-01 289.4320 1544.965 152.68 0.93 EK-81P 548 Yes 253 1.290 19 12 0.080 0.645 0.565 96.7 2.04E-01 313.7540 1536.381 111.91 0.68 EK-86A 846

?

159 0.850 4

12 0.065 0.425 0.36 96.7 1.08E-01 206.7371 1920.528 91.07 0.47 EK -C10 520 Yes 33 0.360 4

12 0.045 0.18 0.135 96.7 2.99E-02 87.5593 2927.953 15.55 0.09 EK-C128 459 Yes 21 0.420 1

.036" 00 0.040 0.21 0.17 96.7 3.21E-02 102.1525 3185.594 14.72 0.07 EK -C13A 1846

?

59 0.349 2

16 0.025

~

0.1745 0.1495 96.7 1.71E-02 84.8838 4967.354 31.55 0.17 L.i>* iii YAR>L ii!>,>>

iii.'

Lei i)'

EK-C18 21750 Yes 1501 0.462 3

16 0.045 0.231 0.186 96.7 3.96E-02 112.3677 2838.429 861.04 4.40 EK-C1C 25168 Yes 2366 0.552 4

16 0.045 0.276 0.231 96.7 4.81 E-02 134.2575 2789.352 1211.39 6.67 EK-C1D 395 Yes 51 0.725 4

16 0.060 0.3625 0.3025 96.7 8.42E-02 176.3346 2094.835 33.25 0.16 EK-C1E 3525 Yes 649 0.837 8

16 0.060 0.4185 0.3585 96.7 9.84E-02 203.5753 2069.845 346.69 1.86 EK-C28 531 Yes 74 0.460 1

18 0.040 0.23 0.19 96.7 3.54E-02 111.8813 3156.700 18.82 0.17 EK-C38 417 Yes 123 0.960 12 18 0.060 0.48 0.42 96.7 1.14E-01 233.4914 2049.567 47.51 0.32 EK-C4A 206 Yes 54 0.930 22 16 0.080 0.465 0.385 96.7 1.43E-01 226.1947 1576.735 29.55 0.16 EK-C7 1485 Yes 68 0.205 22 19 0.025 0.1025 0.0775 96.7 9.49E-03 49.8601 5252.016 14.10 0.15 EK -F1A 3933 Yes 228 0.360 2

16 0.045 0.18 0.135 96.7 2.99E-02 87.5593 2927.953 117.61 0.64 EK -F38 20 Yes 6

0.351 10 16 0.080 0.1755 0.0955 96.7 4.57E-02 85.3703 1866.520 0.91 0.01 EK-G1A 143 Yes 8

0.405 2

14 0.045 0.2025 0.1575 96.7 3.42E-02 98.5042 2882.204 4.89 0.02 EK-G18 1082 Yes 49 0.351 2

18 0.045 0.1755 0.1305 96.7 2.91E-02 85.3703 2938.718 31.43 0.15 EK-G1C 3066 Yes 1021 0.351 10 18 0.080 0.1755 0.0955 96.7 4.57E-02 85.3703 1866.520 140.23 2.17 VFC-11 120

?

3 0.500 1

14 0.045 0.25 0.205 96.7 4.32E-02 121.6101 2815.340 5.18 0.02 VFC-12 80

?

1 0.400 1

14 0.045 0.2 0.155 96.7 3.37E-02 97.2881 2886.714 2.70 0.01

DC00040-110 Revision 0 page 36 of38 File "Calc" per TWR Serial 66006 (Reference 14) Known Cables in the Reactor Building CALCULATED VALUES NUMBER OF Hvpalon 1.55g/cc mH SA SA Total wt

%wt Sum Of Total Insulation Outside Outside Jacket Cable Code Length(ft)

Chlorine Content Weight(lb)

Diameter (inch)

CONDUCTORS CONDSIZE Thickness OR inch OR-OJT density Ib/ft sq cm/ft sq cm/lb jacket Ibs VFC-14 100

?

3 0.620 1

14 0.065 0.31 0.245 96.7 7.61E-02 150.7965 1981.390 7.61 0.02 VFC-18 240 Yes 36 0.575 15 18 0.065 0.2875 0.2225 96.7 6.99E-02 139.8516 1999.719 16.78 0.10 VFC-19 210 Yes 54 0.665 16 16 0.040 0.3325 0.2925 96.7 5.27E-02 161.7414 3066.665 11.08 0.12 VFC-20 180 Yes 75 0.805 26 16 0.040 0.4025 0.3625 96.7 6.46E-02 195.7922 3032.907 11.62 0.16 VFC-21 250 Yes 16 0.122 4

16 0.040 0.061 0.021 96.7 6.92E-03 29.6729 4288.157 1.73 0.03 VFC-22 600

?

10 0.122 1

16 0.040 0.061 0.021 96.7 6.92E-03 29.6729 4288.157 4.15 0.03 VFC-23 145 Yes 37 0.939 16 16 0.080 0.4695 0.3895 96.7 1.45E-01 228.3837 1575.314 21.02 0.11 VFC-24 632

?

17 0.138 1

14 0.040 0.069 0.029 96.7 8.27E-03 33.5644 4058.614 5.23 0.04 VFC-25 190

?

6 0.330 2

16 0.050 0.165 0.115 96.7 2.95E-02 80.2627 2717.507 5.61 0.02 VFC-26 145

?

19 0.138 3

14 0.040 0.069 0.029 96.7 8.27E-03 33.5644 4058.614 1.20 0.04 VFC-44 215 Yes 5

0.242 COAX 0.018 0.121 0.103 96.7 8.51 E-03 58.8593 6919.577 1.83 0.01 VFC-51 95 Yes 7

1.014 12 20 0.065 0.507 0.442 96.7 1.30E-01 246.6252 1895.148 12.36 0.04 VFC-57 160

?

38 0.765 24 18 0.065 0.3825 0.3175 96.7 9.60E-02 186.0634 1938.361 15.36 0.10 VFC-59 60

?

13 0.678 4

12 0.065 0.339 0.274 96.7 8.41E-02 164.9033 1961.736 5.04 0.03 VFC-72 380 Yes 16 0.242 COAX 0.018 0.121 0.103 96.7 8.51E-03 58.8593 6919.577 3.23 0.04 VFC-116 350 Yes 10 0.242 8-SPL 0.018 0.121 0.103 96.7 8.51E-03 58.8593 6919.577 2.98 0.02 VFC-117 100 Yes 4

0.242 10-SPL 0.018 0.121 0.103 96.7 8.51E-03 58.8593 6919.577 0.85 0.01 VFC-118 65

?

1 0.236 6

22 0.025 0.118 0.093 96.7 1.11 E-02 57.4000 5157.916 0.72 0.00 VFC-119 274 Yes 12 0.242 COAX 0.018 0.121 0.103 96.7 8.51E-03 58.8593 6919.577 2.33 0.03 VFC-128 620

?

26 1.000 COAX 0.065 0.5 0.435 96.7 1.28E-01 243.2202 1896.967 79.49 0.20 VFC-133 135

?

2 0.166 2

22 0.025 0.083 0.058 96.7 7.44E-03 40.3745 5429.173 1.00 0.01 VFC-134 18

?

4 0.880 9

14 0.065 0.44 0.375 96.7 1.12E-01 214.0337 1915.122 2.01 0.01 VFC-135 324

?

29 0.450 4

14 0.045 0.225 0.18 96.7 3.84E-02 109.4491 2846.621 12.46 0.08 VFC-136 120

?

2 0.500 8

14 0.045 0.25 0.205 96.7 4.32E-02 121.6101 2815.340 5.18 0.01 VFC-138 380

?

0 0.230 TRIAX 0.018 0.115 0.097 96.7 8.05E-03 55.9406 6948.710 3.06 0.01 VFC-144 55

?

0 1.000 12 12 0.065 0.5 0.435 96.7 1.28E-01 243.2202 1896.967 7.05 0.01 VFC-155 48

?

1 0.200 1-COAX 0.018 0.1 0.082 96.7 6.91E-03 48.6440 7038.349 0.33 0.00 17083.28 100.00 244380 36540 Composite Cables: the largest conductor size has been shown Total cable+insulation unknow 19% increase 53623 0.19 63812

Cables with Unknown Locations DC00040-110 Revision 0 page 37 of38 CALCULATED VALUES NUMBER OF Hypalon 1.55g/cc mH SA SA Total wt

%wt Sum Of Total Insulation Outside Outside Jacket Cable Code Length(ft)

Chlorine Content Weight(lb)

Diameter (inch)

CONDUCTORS CONDSIZE Thickness OR inch OR-OJT density Ib/ft sq cm/ft sq cmllb jacket Ibs CFC-7 5

?

0 0.292 6

22 CFC-8 140

?

18 1.100 COAX CFC-13 140

?

1 0.190 4

24 CFC-16 100

?

10 0.734 100 24 CFC-18 12

?

1 0.650 38 22 CFC-27 60

?

2 0.313 4

18 CFC-36 529

?

10 0.340 15 22 CFC-40 45

?

4 0.600 8

18 CFC-41 70

?

45 0.436 2

16 CFC-50 5

?

0 0.273 6

22 CFC-52 29

?

3 0.675 16 14 CFC-73 1230

?

19 0.188 8

24 CFC-76 410

?

0 1.245 100 22 CFC-82 240

?

2 0.195 8

24 CFC-86 15

?

0 0.660 16 14 EK-A2E 15 Yes 12 1.680 2

4/0 0.090 EK-A2H 36 Yes 42 2.000 3

250 0.110 EK-A2K 185 Yes 158 1.660 3

3/0 2.000 EK-A2M 25 Yes 17 1.430 3

1/0 0.095 EK-A2S 48 Yes 21 1.220 2

1/0 0.080 EK-A3B 13 Yes 4

0.820 2

6 0.065 EK-A3C 3350 Yes 874 0.740 2

8 0.065 EK-A3D 98 Yes 21 0.610 2

10 0.065 EK-A3H 111 Yes 42 0.790 3

8 0.065 EK-A3H 56 Yes 21 0.790 3

8 0.065 EK -A3J 710 Yes 102 0.640 3

10 0.065 EK -A3J 363 Yes 52 0.640 3

10 0.065 EK-A3L 40 Yes 21 1.120 4

4 0.080 EK-A3P 35 Yes 16 1.210 3

1 0.080 EK-A3S 11 Yes 6

1.370 4

1 0.090 EK-B1A 720 Yes 60 0.420 1

9 0.050 EK-B1G 4588 Yes 693 0.610 2

12 0.065 EK-B1G 1620 Yes 245 0.610 2

12 0.065 EK-B1H 142 Yes 24 0.640 3

12 0.065 EK-B1H 89 Yes 15 0.640 3

12 0.065 EK -B1J 2204 Yes 412 0.690 4

12 0.065 EK -B1J 55 Yes 10 0.690 4

12 0.065 EK-B1K 171 Yes 36 0.740 5

12 0.065 EK-B1K 50 Yes 10 0.740 5

12 0.065 EK-B1L 893 Yes 212 0.800 7

12 0.065 EK-B1M 540 Yes 186 1.060 10 12 0.080 EK-B1N 76 Yes 32 1.190 15 12 0.080 EK-B1P 138 Yes 64 1.290 19 12 0.080 EK-B3B 105

?

9 0.440 3

12 EK-C13A 755

?

24 0.349 2

16 0.000 EK-C13A 88

?

3 0.349 2

16 0.000

Cables with Unknown Locations DC00040-110 Revision 0 page 38 of38 CALCULATED VALUES NUMBER OF Hypalon 1.55g/cc mH SA SA Total wt

%wt Sum Of Total Insulation Outside Outside Jacket Cable Code Length(ft)

Chlorine Content Weight(lb)

Diameter (inch)

CONDUCTORS CONDSIZE Thickness OR inch OR-OJT density Ib/ft sq cm/ft sq cm/lb jacket Ibs EK-C1A 6961 Yes 397 0.436 2

16 0.045 EK-C1A 847 Yes 48 0.436 2

16 0.045 EK-C1B 13 Yes 1

0.462 3

16 0.045 EK-C1C 402 Yes 38 0.552 4

16 0.045 EK-C1E 316 Yes 58 0.837 8

16 0.060 EK-C1G 86 Yes 26 1.014 12 16 0.080 EK-C3B 110 Yes 32 0.960 12-SPL 0.060 EK-C7 60 Yes 3

0.205 COAX 0.025 EK-D1C 12985 Yes 429 0.246 1

10 0.015 EK-D1D 660 Yes 20 0.246 1

10 0.015 EK -F3B 20 Yes 6

0.351 10 16 0.080 EK-G1A 372 Yes 21 0.405 2

14 0.045 EK-G1A 246 Yes 14 0.405 2

14 0.045 EK-G1B 688 Yes 31 0.351 2

18 0.045 EK-G1B 12 Yes 1

0.351 2

18 0.045 EK-G1C 410 Yes 137 0.351 10 14 0.080 EK-G1C 18 Yes 6

0.351 10 14 0.080 VFC-4 15 Yes 8

0.690 8

8 0.065 VFC-36 572

?

25 1.000 19 22 VFC-48 180

?

6 0.450 2

16 VFC-73 135 Yes 7

0.351 2SPL 0.045 VFC-130 60

?

9 0.080 1

22 VFC-137 6

?

1 0.453 SPL 0.00 0.00 45534 ratio unknown to RB 19%

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