ML18026A436
| ML18026A436 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/02/1994 |
| From: | Kenny J PENNSYLVANIA POWER & LIGHT CO. |
| To: | James Shea NRC |
| Shared Package | |
| ML17158A157 | List: |
| References | |
| NUDOCS 9403100146 | |
| Download: ML18026A436 (11) | |
Text
A'7/>1'7i 1994 I 5: 79 j
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fi1A-774-79AA PPI I'i1 I('.
I TI'.F NIi ENCLOSURE 5
Pennsylvania Power 8 Light Company AO NOrth NITIth StrNt +AllrnOO/rn, PA 1S101-1179>215/77441M February 2, 1994 Mr. )oseph W, Shea U.S, Nuclear Regulatory Commission Attached is our response to three of the four requests for information on our analySiS Of radiOIOgiCal impacts resulting froTTI the loss of spent fuel pool cooling postulated
- events, We are working on the qgestion of impact of refueling floor drains on operator exposure and expect to have results by the end of the week, You will note some of the information is draft in that it is not tn a finished calculation. Ifthere are substantive changes in the finished calculation, l will provide you with a revised document.
Any questions please cail me at 610-774-7904, 4m~
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J as M. Kenny yj Attachment 9aosi00146 940228
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618-774-7968 PPL NLC LIC SVS)UEHAIOA STEAN ELECTRIC STATION UNITS 1 4 2 CONTAIHHBiT ILRT RESULTS BASED ON TOTAl TINE I 954 UPPER CONFIDENCE LINIT ILRT TEST DATE 5 5 92 5 30 89 6
1 85 NIT 1 CONYAINENT ILRT RESULTS AS-FOUND CONTAINNENT LEAKAGE RATE d
0.716 0.745 0.755 AS-LEFT CONTAINMENT LEAKAGE RATE da 0.606 0.665 O,I25 ILRT TEST DATE 10 31 92 11 3 89 6 1086 11 2 83 UNIT 2 CONTAINNKMT ILRT RESULTS AS-FQUNO CONTAINENT LEAKAGE RATE da 0.4S1 0.515 2.6 AS-LEFT CONTAINMENT LEAKAGE RATE Xd 0.337 0,471 0.629 O.132 The primary containment design 1eakage rate is 1 +day.
For the FSAR licdnsing basis DSA-LOCA analysis th1s leakage rate fs assumed for the duration of the accident.
For the analysis of operator access doses inside the reactor building to address postulated post-LOCA fuel pool boiling concerns, a time dependent realistic containment leakage rate based on containment Integrated Leakage Rate Testing (ILRT) results and the calculated containment post-LOCA pressure response is used for both the clad damage and 100% fuel melt cases.
The ILRT test pressure corresponds to the maximum calculated containment post-LOCA pressure with a
design margin applied.
The realistic containment leakage rate was calculated by reducing the ILRT measured leakage. rate proportionately to the ILRT test pressure and the calculated containment pressure response for a LOCA.
A comparison of ILRT tost results for Units 1 and 2 for leakage tests performed since 19S3 is given in the above Tables.
It can be sean that measured leakage rates vary between 0.337
%/day and 2.60 %/day.
For the analysis of operator access doses 1nside the reactor building to address postulated post-LOCA fuel pool boiling concerns, tho most up-to-date leakage rate data was used so that the dose estimates reflect the most up-to-date containment leakage cond1tions.
Therefore, the measur ed leakage rate of 0.606%/day from the Unit 1 ILRT performed 5/5/92 was assumed.
With the exception of tho Unit 2 test dated 6/10/86 where two conta1nment isolat1on valves failed to
- seal, 0.606%/day is also representative of typical measured leakage rates at SSES Units 1 L 2 as can be seen by comparing the test results given above.
QUAN OF CALCUiATMOPNATOR NXESS QOSES TO CHECK SPENT FUEL POOL MATER LEVEL REhCTOR BUILOIlS UNITS 1 5 2 REFUELING FMN ELEVATION 81S'-1'PERATOR ACCESS DOSES AT 24 HOURS POST-LOCA (R) 1$$ CLIO MQQK 1% CLN QQlASE (1) aom ae. m.r DOSE LOCATION/
SOURCE Dose Free Airbone Activity Dose Froa Contained Sources Dose Free Airborne Activity Dose Free Contained Sources Dose Froa Airborne Activity Dose Froa Contained Sources Ol Ingress/Egress To Refueling Floor -- Elev. 818'-1 Operator Stay TiNe On Refueling Floor -- Elev. 818'-1st 2
Totals Total I ress E ress Total erator Sta Time 0.0584 0.0973 0.156 0.0728 0.0923
- 0. 0144 0.
0.0144 5.84-4 9.73-4 1.56-3 7.28-4 9.73-4 1.44-4 D.
1.44-4 1.59B
- 2. 66 4.258 1.744 2.66 0.146
- 0. 146 C~
IIM Cs TOTAL ACCESS DOSE 0.17 1.70-3 4.40 NTES:
(1)
Post-LOCA radiation doses for the 1% clad daaage case are obtained by eultiplying the INC clad daaa n
doses by a factor of D.01 (2)
A total stay tine at the spent fuel pools of tuo niautes is used and is based on conservatively assunlng that one ainute is required at each spent fuel pool to check the rater level.
PA6E 85 S~ry Qf TACTS Casputet'ode Output Kdht At End Of 2i Hays
, B~/B2/1994 15:29 61B-7
-796)
PPL NUC LE
~
9 l I
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'POST-LOCA ACTIVITY SONCE TNNS IN REACTOR IUILDINQAN SUPNESSMl POOL CONTAINNENT LEAKAGE
~
0.0371%/DAY 0 CONTAINMENT TEST PRESSURE OF 45.
PSIG (BASED ON MEASURED DATA MITH AIR SEAL LEAKAGE ONLY'EAKAGE REDUCED FOR CONTAINMENT PRESSURE DECAY)
CONTAIHHENT POST-LOCA PRESSURE l TENPERATURE:
FSAR FIGURES S.g-g, 6.2-3 POST-lOCA ACTIVITY RELEASE:
REGULATORY GUIDE 1.3 ESF LEAKAGE INSIDE REACTOR BUILDING:
NONE REACTOR BUILDING NODE lS LABELED SUPPRESSiON POOL NODE IS LABELED NOTRE The TACTS act4v4ty source terms 11sted below for th1s case were used to evaluate o orator access doses 1nstde the reactor bu1ld1 ACTIVITY RELEASED TO ENVIRONMENT AND ZN EACH NODE AT END OP 2 ~ 40OE+Ol (HRS)
ZSO NAN Z
131 Z
131 Z
131 Z
132 Z
132 I
132 X
133 Z
133 Z
133 Z
134 I
134 Z
134 Z
135 Z
135 135 XR 83M ER 85M KR 85 KR 7
KR 88 KR 89 XE 131M XE 133M XE 133 XE 135M XE 135 XE 137 XE 138 ENV.
li736E+03 7 531B+01 9 ~ 539E+01 3 '08E+02, 1+53OE+01 2 ~ 037 E+01
- 2. 786E+03 lo224E+02
- l. 531E+01 2o348E+02 1.031E+01 1 290E+01 1o342E+03 5 '98E+01 7 ~ 372E+01 4 e 269E+02 4.758Z+03
- 9. 100E+01 1.333E+03 6 '66E+03 4 191E+01 5 ~ 551K+ON 1 ~ 558K+03
- l. 153E+05 9 892E+01 4 475E+04 do568B+01 3 '74'8+01 PRZ CONT 1.808E+07 7 '49B+05 9 ~ 936E+05 2 ~ 361E+04
- 1. 0388+03 le297E+03 le992E+07 8.755E+05 le095E+06 2.255E 01 9.911E-03 1 ~ 2398-02 3 '77E+06 1.484E+05 1 $55E+05 1.875E+03 lo014E+05 1 '17E+05 1.51OE+02 1 909E+05.
0 ~ OOOE-01 8 '61E+05 3 '3dE+05 1 ~ 703E+08 9 '96E-21 3 '39K+07 O. OOOE-01 5 '08E-18 SBC CONT 7e545E+03 3o350E+02 4 ~ 200E+02 9 '79E+00 4.3$ 7E 01 5 '83E~01 8 o 421E+03 3 '702E+02 4 ~ 527E+02 9.532E 05 4.19OE 05 5'37E-05 1.428E+03, 6e275E+01
- 7. 844E+01 7.926E 01 4.285E+02 5 '89E+02 6.07E-O2 1 230E+02 0
OOOE~OL 3 '77E+02 le495B+03 7.1988+04 3 '88E-14 li285E+04 Oo OOOE 01 Qi2028 11 SUP POOh
- 3. 621E+07 1.591B+06 1 ~ 9$9E+06 4.715E+04 2 ~ 078E+03 2 '97E+03 3 '88B+07 1.753E+05 2 ~ 191E+06 4 '14E-01 1 9$ 4E 02 2 '80E~02 d e 751E+05 2 ~ 972E+05 3o715E+05 4 '18E-18 1'65E 25 6 409E-21 F 4528-29 5 '96E~26 0 ~ OOOE-01 1.265E-24 1+266E-24 1 136E-22 0+OOOE Ol 4.782E-14 0 ~ OOOE 01 0 o OOOE~01
18 k
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PPL PIC LE PAGE 86 Sugary Of TACTS Coayuter Code Output Ed)t At End Of 2i Hours eg/82/1994 15: 29 618-7
-7968
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P05T-LOCA ACTIVITYMNCK TERN5 IN REACTOR NIU)INNO SUPPRE55IN POOL CONTAIRNKNT LEAKAGE
~
0.0371%/DAY P CONTAINNENT lEST PRESSURE OF 45.
PSIG (BASED ON MEASURED DATA ARITH AIR SEAL LEAKAGE ONLY; LEAKAGE REDUCED FOR CONTAINMENT POST-LOCA PRESSURE DECAY)
CONTAINNENT POST-LOCA PRESSURE L TENPERATURE:
FSAR FIGURES 6.2-2, 5.2-3 POST-LOCA ACTIVITY RELEASE; REGULATORY GUIOK l,3 ESF LEAKAGE INSIDE REACTOR BUILDING; 5 gpss REACTOR BUILDING NODE IS LABELED Qf~g+
SUPPRESSION POOL ROOK IS LABELEO QP~jQ, NTEi The TACTS act1v1ty source tertms l1sted below for th1s case wore not used to evaluate operator access doses 1ns1de the reactor bu1ld1ng and are rov1ded for knformat1on onl ACTIVITY RELEASED TO ENVIRONMENT AND IN BACH NODE AT END OP.
~ ~
2 ~ 400B+01 (HRS)
131 I
131 I
131 I
132 I
132 I
132 I
133 I
133 I
133 I
134 I
134 I
134 I
135 I
135 135 gR 83M KR 85M ER 85 KR 87 ER 88 KR 89 XE 131M XE 133M XE 133 XB 135M XE 135 XE 137 XE 138 BNV.
PRI CONT SBC CONT 1.896E+03 1e808E+07 1.936E+04 8e332E+01 7o949B+05 Q.SOQE+02 lo042E+02 9.936B+05 1e064E+03 3 i 847E+02 2 ~ 361E+04 2. 527E+01 1 ~ 691E+01 1 ~ 038E+03 l.111E+00
- 2. 114K+01 1 o 297E+03
- 1. 389E+00 3 '21K+03 1.992E+07 Rel33B+04 1.328E+02 8.756E+05 9 374E+02 1o660B+02 1.095E+06 le172Et03 2 '90E+02 2o255B-01 2.414E 04 1.05OE+01 9 '11E-03 1.061E 05 1o313E+01 1.239B 02 le 326E 05 1.432E+03 3 ~ 377E+06 3 ~ d15B+03 6 ~ 294E+01 1 484m+05 1.589B+02 7.8d8Z+01 1 ~ 855R+05 1.98dE+02 4.269B+OR li875E+03 7 926E-01 4.768Z+03 1.014r+06 4.285E+02 9.100E+02 1.417E+06 5 989E+02 1 ~ 333E+03 1 ~ 610E+02 6 ~ 807E-OR 6.166R+03 2 909E+05, 1.230K+02 4e191E+01 0
OOOE 01 0 ~ OOOE 01 5.561E+02 8.461E+05 3 ~ $77B+02 2.568B+03 3.536E+06 1.495E+03 1 ~ 153E+05 1o703E+08 7 '98E+04 9 '92E+01 9.196E-21 3'88B 24 4e475E+04 3 '39E+07 li285E+04 6 ~ 668E+01 0 ~ 404R-. 01 0 ~ OOOE 01 3 ~ 374B+42 5.208B-18 2 ~ 202E 21 SUP POOL 3 '93E+07 1.580E+06 1.974E+06 4.691E+04 Ro062E+03 2.577E+03 3 '59B+07 1.740E+06 2.175B+06 4o481B 01 le969E-02 2 'd2E-02 6 '10B+06 2.950E+05 3i687E+05 0 ~ OOOE 01 5'74B 29 8 '05E-30 0 ~ OOOE 01 3 '57E-29 O.OOOE-01 5 '85E 30 3.229K-R9 1.373B-27 0 ~ OOOE-O1 7 '7QE 2$
0 ~ OOOE-01 0 ~ 000E~01
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A7 POST-LOCA ACTIVITY SOURCE TERNS IN REACTM NILQININS SUPPRESSION POOL S~ary Of TACTS Coeputer Code Output Ed)t At End Of 24 Hours CONTAIQIENT LEAKAGE
~ 1,0%/DAY I CONTAINMENT DESIGN PRESSURE OF 53.
PSIG (DESIGN LEAKAGE REDUCED FOR CONTAINENT PRESSVRE OECAY).
CONTAINNENT POST-LOCA PRESSURE L TENPERATVRE:
FSAR FIGURES 6.2-2, 6.2-3 POST-LOCA ACTIVITY RELEASE:
REGULATORY QJIDE 1.3 ESF LEAKAGE INSIDE REACTOR BUILDING:
NNE REACTOR BUILDING NODE IS LABELED~gg StJPPRESSION POOL HOOE IS LABELEO ~?Qg, NOTE> The TACT5 activity source tares listed below for this case were not used to evaluate operator access doses inside the reactor building and are rovided for information onl ACTIVITYREbZhSKD TO ENVDLONHKNT AND ZN ShCH NOM AT ENO OP ~ ~.
2 ~ 400E+01 (HRS)
ISO NAH 131 f:
131 X
131 I
132 I
132 132 I
133 133 X
133 E
134 134 I
134 135 135 I
135 KR 83%
XR 8SN KR 85 XR 87 gR 88 KR 89 XE 131M XZ 133M XE 133 XE 135M XE 135 XE l37 XE 138 ENVe PRZ COST SEC CONT 2 4755+03 1 750K+07 d ~ 20251'Oi
- l. 088K+02 7.893i+05 2 ~ 725E+03 1 o 360K+02 9 ~ 057XM5 3 ~ 4DIE+43 4e356E+02 2.344B+04 8e096R+OX 1 ~ 919K+01 lo030R+03 3 ~ 5598+00 2o399E+Ol 1.288E+03 4 '49E+00 3.876E+03 1 ~ 9785+97 5.832@+44 1+704E+02 8 '95E+05 3+003K+03 2.129E+02 1 087E+06 3 '545+03 2.5525+02 2 ~ 239B-01 7 ~ 733E 04 1.122E+01 9 '42E-03 3.399E 05 le402E+01 1 230E 02 4 '49E-05 1.752K+03 3 '53E+05 1.158E+04 7 7448+01 1'74E+05 Se091E+02 9 '80K+01 lo842R+05 5.3635+02 2 '17E+03 1.852E+03 6+430E+00 3 '90E+04 1 007B+05 3.477E+03 5 5458+03 loi078+Od 4.059K+03 7.175E+03 1.599m+02 5.523E 01 3 '118+04 2 '89E+05 9 '78E+02 7.438m+01 0 ~ OOOE 01 OoOOOE-01 3.997K+03 8 ~ 402m+05 2 ~ 902E+03 1.840E+04 3 ~ 512E+06 1.213E+04 8+278E+05 led91E+0! So840E+05 2.992R+02 9 132E-21 3.154E 23 3.126E+05 3.018E+07 1.042E+05 1 ~ 257K+02 0 ~ OOOE-01 0 ~ OOOE 01 1 ~ 057E+03 5 1725~18 1 7mdB 20 SUP POOL 3 d21E+D7 1oS91X+06 1o$ 19K+Od 4.726E+04 2 '78K+03 2 '97E+03 3 '888+07 1 753E+05 2 ~ 191K+06 4e514i 01 lo984E 02 2'808-02 do761E+06 2 972E+05 3e71SE+05
- 4. 821E-28 1o733E 25 6 6798-22 5'04K 29
- a. OOOi-Ol 0 ~ OOOE-Oi
t
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'Og-LOCA ACTIVITY SOURCE THNS IN REACTM IUILDINNS 5UPPRESSIN POOL
%mary Of TACTS Ceeputer Code Output Ed1t At Knd Of 24 Hours CONTAINMENT LEAKAGE
~
0.606%/DAY I CNTAINNENT TEST PRESSURE OF 45.
PS16 (BASED ON HEASURED ILRT DATA; LEAKAGE REDUCED FOR CONTAIHNENT POST-LOCA PRKSSURE DECAY)
CONTAINENT POST-LOCA PRESSURE 4 TEHPERATURK:
FSAR FIGURES 5.2-2, 6.2-3 POST-LOCA ACTiVITY RELEASE:
REGULATORY GUIDE 1,3 ESF LEAKAGE INSIDE REACTOR BUILDING:
NONE REACTOR BUILDING NOOK IS LABELED SUPPRESSIN POOL NODE IS LABELED NTKa The TACTS actfvfky source terms 1fsted below for thfs case'ware not usod to evaluate operator access doses fnsfde the reactor bufldfnm and are rovfdod for 1nformatfon onl ACTXVZTX RELEASED TO ENVIRONMENT AND ZN EllCH NODE hT Zm Or...
2.400E+01 (HRS)
I31 I
131 I
131 I
132 I
132 I
132 I
133 I
133 I
133 I
134 I
134 I
134 I
135 I
135 I
135 KR 13%
KR 85H KR QS KR 87 KR 89 XS 131H XE 133M XE 133 XB 135M XR 135 XR 137 XR 130 ENV.
PRI CONT 8EC CONT 2 ~ 173E+03 1 ~ 801K+07 3o989E+04 9o554E+01 7o916B+05 1.754E+03
- 1. 194B+02 9. 895B+05 2 i 192E+03 4.097E+02 2.351K+04 5.208E+01 1.801E+Ol le033E+03 2 '898+00 2 ~ 251E+01 1 292B+03 2 ~ 861E+00 3 ~ 431E+03 1 ~ 984E+07 4 ~ 395E+04 1 e 508E+02 8 ~ 72OE+05 1 ~ 932E+03 1 e 885E+02 1 ~ 090E+06 2 ~ 415E+03 2.l68E+02 2 '45E-Ol. 4o974E 04 lo085E+01 9o870E-03
- 2. 186E 05 1.356B+dl 1 234E 02 2'33E 05 1.590E+03 3i363E+Od 7.450E+03 6 OQOR+Ol 1.4'78%+05 3.275K+02 Se738E+01 1.848E+05 4+093E+02
- 1. 662X4 03 1. 867R+03 4. 136E+00 2 ~ 081E+04 I..010K+06 2 ~ 236E+03 4 ~ 24dB+03 1. 411E+Od 3. 125%+d3 4 ~ 785E+03 1 ~ 604E+OQ 3 ~ 552E-O1 2 ~ 564R+44 2. $97R+05 6 ~ 418E+02 6 ~ 2288+01 0 ~ OOOE-OI: 0 ~ 0008~01 2 '93B+d3
$.426K+45 1
$67R+d3 1o194E+04 3 ~ 522K+06 1.801E+03 5.371R405 1.d9dR+OS 3-756E+05 2 '73E+02 9 '58E-21 2 029E 23 2.033R+OS 3 '27B+07 6.1058+44 1 ~ 022E+02 0 ~ OOOE 01 0 ~ OOOE-01 7 625K+02 5.106m 18 1.149K-20 SUP POOL 3 '21E+07 1.591E+06 Xo9898+06 4e726E+04 2 '78E+03 2 '97E+03 3.988B+07 lo753B+06 2 '918+06
- 4. 5148-Ol 1.984E-02 2.480E 02
- 6. 761Z406 2 972B+05 3 '15E+05 4.$ 02% 2$
1.726E 25 6.641B 22 5 ~ 681E 29 6.0138~26 0 ~ OOOE-01 1.31OE 24 1 '22B-24 1.177E 22 OoOOOE-01 4.952E 24 0 ~ OOOE-01 0 OOOE-01
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