ML20032E898
| ML20032E898 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 10/16/1981 |
| From: | Fulton J BOSTON EDISON CO. |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| 81-252, NUDOCS 8111230477 | |
| Download: ML20032E898 (24) | |
Text
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9 BOSTON EDISDN COMPANY LE E N E R AL O FFICE E G OD B OYLETOi4 STRE ET G O E T O N. MA5 5 ACHUG ETTS O219 9 A. V. M O RISI MANADER NUCL EAR O PERATIOrda SU PPORT DEPARTM ENT October 16, 1981 BECo. Ltr. # 81-252._
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- ir. Thomas A. Ippolito, Chief
/i/ NOV2 01987 Operating Reactors Branch #2 Division of Licensing
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lH W8 N>%, a Office of Nuclear Reactor Reguhtion 4
U.S. Nuclear Regulator 3 Commission h
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4 Washington, D.C.
20555 7
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p License No.
D Docket No.
50-293 Response to Request for Additional
_Iplormation Concerning Containment AP.osphere Dilution (CAD) System
Reference:
Telepnone conference conducted on October 15, 1981, between Mr. Mark Williams, Mr. Richard Kendall and Mr. Lawrence Ruth of NRC, and Mr. Robert Tracy, Mr. John Coughlin and Mr. P.M. Kahler of Boston Edison.
Dear Sir:
In the referenced telephone conversation, it was indicated that addi-tional information would serve to clari'y certain aspects of Boston AOOg Edison's previous submittal concarning the CAD system of Pilgrim p 5 Station.
We believe the accompanying attachments will satisfy that request.
Should you have need of any further information regarding this issue, please contact us.
Very truly yours, A.f
@g,m A
Attachments:
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- PNPS Proc. No. 5.4.6 " Post Accident Venting"
- Calculations for H2 Vol % after LOCA
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- BOS~ON 'A #dtSOIl COMNdY
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NUCI.E.e O?I?AT!C55 DI?ARTMENT PILGRDd. hCC EAR FOL'IR STATION Procedure No.
5.4.6 POST ACCIDEh*T VENTING List of Effective Pages_
4 5.4.6-1 Rev. 9 5.4.6-2,Rev. 8 5.4.6-3 Rev. 9 Attachments _
5.4.6A-1 Rev. 0 l '.
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Approved RC Ch r an
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5.4.6-1 Rev. 9
I I.
SYMPTOMS A.
Drywell pressure 30 psi and increasing.
(?r' B.
Hydrogen concentration greater than 2%.
II.
AUTOMATIC ACTION Reactor vessel low, low water level trip seals in an isolation signal and there is no " override" for this signal.
NOTE: There is no isolation logic associated with the containment purge and vent valves controlled from the PAM panels 0-170 and C-171.
III. 'IMfEDIATE OPERATOR RESPONSE - NITROGEN INERTED PRIMARY CONTAINMENT A.
Assure that the primary containment and secondary containment are properly isolated and that the Standby Cas Treatment System is in service.
B.
Isolate city water to SBGTS spary' system by securing bleek valve in makeup demin area to prevent inadvertent spray of the charcoal.
C.
Place the H Analyzers in service and determine hydrogen concentration 2
par procedure 7.4.19.
See P&ID M-239.
D.
Order nitrogen truck from any vendor on Attachment "A".
E.
When the H, concentration approaches 2%, but within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after an accident, 5 pen the following N make-up valves to add nitrogan to the
(
containment. See P&ID M-227. y Nitrogen may come from non-seismic nitrogen tank if available or from truck nitrogen.
NOTE: If nitrogen is not available, service air may be used.
Keep inlet pressure between 65-70 psig to assure that at least 30 scfm of nitrogen is entering both drywell and torus.
OPEN EITHER TRAIN "A" OR 3" SOLENOID PURGE VALVES DRYWELL TORUS _
~
SV-5085 SV-5087 SV-5086 SV-5088 F.
Prevent drywell and torus pressures from dropping below 22 psig 'by nitrogen (or service air) addition.
~
G.
Monitor Hydrogen concentration and maintain below 4% by continued addition of nitrogen (or service air) up to a maximum pressure of 28 psig.
H.
Maintain drywell and torus pressures between 22 to 28 psig by nitrogen additioner by venting through vent solenoid valves:
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3.4.6-2 Rev. 8
___.._ _. - _ _, ~ _ -, _ - -, _ _, _. -. _ _ _. _,
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OPEN EITHER TRAIN "A" OR "B" SOLEN 0_ID VQT VALV TORUS DRYWELL SV-5053 SV-5081 07-5084 SV-5082 d t and At least 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> must have elapsed since the acci en l before venting meteorological conditions must be acceptab eThe meteorological cond CAUTION:
i procedure operations can commence.shall be checked and off site doses estima 5.7.2.23 (Off Site Dose Rate Estimates).
entation.
Monitor the discharge by observing the following instrum d section of the I.
Monitor and record the released dose at the downwin 1.
site boundary.
d record the Monitor the effluents released through the main stack an 2;
activity level of the releasw.
hile venting is Maintain close surveillance on all radiation monitors wTh 3.
monitor should be used to cross check and in progress.
DISCUSSION direction of the Emergency V.
Emergency pest accident venting is performed at the t the primary containment Director and is required end permitted only to prewnfro ure) or to i ary containment (for a control combustible gas mixtures inside the pr mn gas concentrations must d
combustible mixture, both the oxygen and hy rogeless than 4%, a combustible mixture deltyed exceed 4% - if either gas concentration isEmergency post accident ven does not exist).
as long as practical and when performed, the ven during periods of of f-shore winds.
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ATTACHMENT A L
NITROGEN SUPPLIERS l..
1 AIRCO l-518-439-8181-6 Act on, Mass.
(71 miles)
O LINDE l-894-7065 Sudbury, Mess.
(65 miles)
MASS OXYGEN 1-366-8361 Westborough, Me (80 miles)
TAUNTON OXYGEN 1-824-6978 Taunton, Mass.
(40 miles) i
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Pp 12 */ & ag j[ V CC 7* c 'il d l I l l l l 90 CASE (e) TWO RHR LOOPS, SUPPRESSION POOL COOLING MODE (b) ONE RHR LOOP,SUPfRESSION POOL COOUNG MODE 40 (c) ONE RHR LOOP. CONTAINMENT SPRAY MODE -r. 4 c, s t g E t = e-30~ E 5 aM sg u ~ l %I WETVWELL -..-- g e ja (a) t TC ~. _ ',,. j (c) [ ___1_. 3,, _ -l-. 7 .l l l l 0 1 2 3 4 5 10'I 10 10 10 .=s' 10 10 1 5 10 106 g TIME Ah5R ACCtDENT (sec) h5? u.6 he -/ t y'$ r o r' -.- j{ ! -, - /,//. f/ >
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i f PILGRIM NUCLEAR POWER STATION FINAL SAFETY ANALYSIS REPORT 1 loss of Coolant Accident, Prinury Containnwnt Prenure Responic FIGL RE 14.0-31
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O PILGRIM NUCLEAR POWER STATION FINAL SAFETY ANALYSIS R2 PORT Loss of Coolant Accident,Suppreuion Pool Temperature Re3ponse FIGURE 14.0 33 I g
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4 J $.y 4 i. Mr e 1 2 10 10 h i i i iiigi i i 8 r - - a'-- --- i iiiisig i i i i i ilij i g i i ii sig eiiiij i i 1 i i i'si' .Liyb a ted. t 8 4 6 l l At 2511 Mw(t) m ~ i r ' ~. -- Co ra a u. 4 4 N j Pn 4 A #m 6 cp y e..,( r) ** Tee I l A cod e r c o,- /,. r., s o, 9 g [,, i ~ w 2 U l 2 o .Q g" J.t r.apigted .... _ _ _. 2 _.!.+ ..- -- -1. - q (3 ~ 4 t 0 - '^- r --- _ -..r * - '--'--'---d C=----.--.--- 10 --suppression Pool; 1 10 d y ~5 g _- k] IF O g I { 6 E ~ e I i wm i wo ZW 4-a c :n wa 70 ~ oo o ci p gg p o 2 .- s g,, o i -m e oz i;3 10.i 10 ,g zm 0 z os C-o~ o F 8 ro c-. H 6- -z D-1 6 o 4., .. -..-- - --_- -.]-- + o 6 i, 4 g I w i 2 4 ~ 10-2 2 4 I g_'. _.. h 1 8 i 1 8 I 6 [ 4 d O'3 I I ! I II!I I I II!!IIl I I I I iI!l l l t l !l tll i l l l l ll! t l l I l t 1T 4'1o 10-2 jo-1 30 io 10 10 10 0 l"- 2 3 8 TIME AFTER ACCIDENT (HR) - hi. m .."Y FIGURE III HYDROGEN GENERATION RATE .[a .1 It W' W i w 1 o ;l 8, 4 P jl 00 '
~~ ~ f Py 17.,,,c ig --~.-...:... = NEDE-24011-P-2 CE COMPAMY PROPRIETARY Class III ( Table 2-1 (Continued) PARAMETERS VARYING WITH ACTIVE FUEL LENGTH, FUEL ASSDiBLY DESIGN, AND REACT 02 TYPE, 8 x 8 BUNDLE DESIGN l Lj 5.b Fuel Assembly Active Fuel Length (in.) [14 -14 6-Heat Transfer Area (f t ) 97.6 98.9 Weight of UD IE8) 2 208.2 211.1 8DB250 208.2 211.1 8DB262 208.0-210.9 SDB274L 207.8 210.7 8DB274H 207.9 210.8 8DB219L 207.7 210.6 8DB219H Weight of U (Kg) 8DB250 183.5 186.1 8DB262 183.5 186.1 183.4 185.9 \\ BDB274L 8DB274H 183.2 185.7 183.3-185.8 8DB219L 183.1 185.6 8DB219H Finger Springs no* BWR/2, 3 Reactors BWR/4 Reactors yes Spacer PJtch (in.) 19.55 BWR/2,3 Reactors EWR/4 Reactors 20.55 Fuel Rods Gas Plenum Length (in.) 11.24 BWR/2,3 Reactors 16 14 BWR/4 Reactors I.
- Yes for Pilgrim and selected fuct assemblics for bypass flow control on other BUR /2 and BWR/3 reactors.
.. _.. _. _.. ~ _ _..
p yg _ _ _.r _._......._m.....-a-NEDE-24011-P-1 ( CE COMPANY FROPRIETARY Class III y-( Table 2-1 ~ ~ FUEL ASSDiBLY DESIGN SPECIFICATIONS PARAMLTERS COMMON TO ALL ASSDiBLY DESIGNS FOR EACH BUNDLE TYPE Fuel Assembly 3 9 Ib Fuel Bundle 8x8 8 x 8R Ceometry 8x8 8x8 Rod Pitch (in.) 0.640 0.640 Fuel Rods ~ Fill Gas helium helium Getter e_s ,yes Number of Fuel Rods 3.
- L62, Fuel Material sintered UO sintered UO 2
2 Pellet Diameter (in.) 0.416 0.410 ( Pellet Length (in.) 0.420 0.410 3 Pellet Ic:=ersion Density (%TD) 95.0 95.0 4 '1 N,,~ t e,.2} Vs 3p. 9'goLh e O s Cladding j. n, g. Hattrial (a Zr-2_ Zr. 2,.,, Outside Diameter (in.) (O 493, y [g.483, S 0 ,90 Thickness 0._03 4,, D22 g. til.,, i Water Rod us L2" Material Zr-2 Zr-2 Outside Dia=cter (in.) 0.493 0.591 Thickness 0.034 0.030 Number of Water Rods 1 2 Spacers Mata. rial Zr-4 with Zr-4 with Inconel X-750 Springs Inconel X-750 Spring Number per bundle 7 7 ,ruel Channel Material Zr-4 Zr-4 Inside Dimension (in.) 5.278 5.278 Wall Thickness (in.) 0.080 0.080 3 or or i 0.100 0.100 \\ l}}