ML17312A609
| ML17312A609 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/07/1996 |
| From: | Stewart W ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 102-03620-WLS-S, 102-3620-WLS-S, NUDOCS 9603180137 | |
| Download: ML17312A609 (14) | |
Text
ACCESSION NBR:960 FACIL:STN-50-528 STN-50-529 STN-50-530 AUTH.NAME STEWART,W.L.
RECIP.NAME DOC KE'g g
05000528 05000/29 050005'30 3180137 DOC.DATE: 96/03/07 NOTARIZED: NO Palo Verde Nuclear Station, Unit 1, Arizona Publi Palo Verde Nuclear Station, Unit 2, Arizona Publi Palo Verde Nuclear Station, Unit 3, Arizona Publi AUTHOR AFFILIATION
-Arizona Public Service Co.
(formerly Arizona Nuclear Power RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards revised pages 1-5,2-5,2-6 6
UFSAR page 15.6-73 associated w/util 950502 submittal requesting NRC review
'pproval of change to larke break LOCA dose consequences for plant.
DISTRIBUTION CODE:
A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution NOTES:STANDARDIZED PLANT Standardized plant.
Standardized plant.
RECIPIENT ID CODE/NAME PD4-2 LA HOLIAN, B INTERNAL: ACRS NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT EXTERNAL: NOAC COPIES LTTR ENCL 1
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1 RECIPIENT ID CODE/NAME PD4-2 PD THOMASiC FILrE CENT NRR DRCH/HICB NRR/DSSA/SRXB OGC/HDS2 NRC PDR COPIES LTTR ENCL.
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NOTE TO ALL "RIDS" RECIPIENTS:.
PLEASE HELP US TO REDUCE WASTEl CONTACT THE DOCUMENT CONTROL DESKI ROOM OWFN SD-5(EXT ~ 415-2083)
TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
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LTTR 19 ENCI 18
WILLIAML STEWART EXECUTIVEVICE PRESIDENT NUCLEAR Arizona Public Service PALO VERDE NUCLEAR GENERATING STATION P.O. BOX 52034 PHOENIX. ARIZONA 85072-2034 102-03620-WLS/SAB/GAM March 7, 1996 U. S. Nuclear Regulatory Commission ATIN': Document Control Desk Mail Station P1-37 Washington, DC 20555-0001
References:
(1)
Letter 102-03345, dated May 2, 1995, from W. L. Stewart, Executive Vice President
- Nuclear,
Letter 102-03578, dated January 5,
- 1996, from W.
L. Stewart, Executive Vice President
- Nuclear, APS, to USNRC, "Proposed Amendments to Facility Operating Licenses and to Technical Specifications and Various Bases, Related to Power Uprate"
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units1,2, and 3 Docket Nos. STN 50-528/529/530 Supplement to Loss of Coolant Accident (LOCA)
Dose Consequences In Reference 1, Arizona Public Service Company (APS) requested NRC review and approval of a change to the large break loss of coolant accident (LOCA) dose consequences for PVNGS due to a new identiTied release path through a depressurized secondary system.
In Reference 2, APS stated that an evaluation was being performed of the LOCA dose consequences related to power uprate and that the NRC would be notiTied ifthe dose consequences exceeded those reported in Reference 1.
During this evaluation it was identified that the base calculation, upon which the Reference 1 dose values were calculated, contained an error.
The error was the omission of the low population zone (LPZ) X/Q value for the time period from 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> to 30 days following an accident.
The original version of this calculation, the source of the original design basis large break LOCA dose consequences, did not contain this error.
The calculation performed to account for the new release path discussed in Reference 1
ratioed the results of the base calculation to account for the increased release through the depressurized secondary system.
As such, this calculation carried over the previous error. The base calculation has now been revised to correct the error. The revised
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U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Supplement to LOCA Dose Consequences Page 2 calculation identified an increase of the LPZ 30-day thyroid dose from 149.7
- rem, reported in Reference 1, to 186.5 rem, which remains lower than the 10 CFR 100 limitof 300 rem. The LPZ 30-day whole body dose increased from 1.46
- rem, reported in Reference 1, to 1.5 rem, which remains lower than the 10 CFR 100 limit of 25 rem.
Included as-an enclosure to this letter are revised pages to the Reference 1 letter with the corrected dose values.'n Section D.6 of Reference 2, it was identified that a new source term was used for LOCA calculations associated with the power uprate project, and, as discussed
- above, that a detailed evaluation of the revised source term inventories was being performed.
That evaluation has been completed, and the identified LOCA doses associated with power uprate are less than those reported in Reference 1 as revised by this sub'mittal.
Should you have any questions, please contact Scott A. Bauer at (602) 393-5978.
Sincerely, WLS/SAB/GAM/rv
Enclosure:
Revised Pages 1-5, 2-5, 2-6, and UFSAR page 15.6-73 Associated with APS Submittal No. 102-03345, Dated May 2, 1995, to USNRC cc:
L. J. Callan K. E. Perkins B. E. Holian K. E. Johnston
t II I
ENCLOSURE Revised Pages 1-5, 2-5, 2-6, and UFSAR page 15.6-73 Associated with Enclosures to APS Submittal No. 102-03345, Dated May 2, 1995
E A
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Table 1-1 LOCA DOSE COMPARISON
SUMMARY
e A. Previous APS Cele'No secondary depressurlzathn)
B. NRC Calculated Valuesb C. Revised APS Cele (Assuming secondary depressurlzation)
D. 10 CFR 100 or 10 CFR 50, GDC 19 Criteria Thyroid Dose EAB (2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />)
LPZ (30 day) 104 9d 132.8 188.5d Cntrl Rm (30 day) 7.0
<10.0 17.2 INhale Body Dose EAB (2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />)
LPZ (30 day)
Control Room (30 day) 1.0 0.95
<2.6
<1.2
<1.0 3.98 1.5 1.472 25 Beta Skin Dose v ues rn rem Control Room (30 day) 19.1 29.67 APS calculations 13.NC-ZY-205, Revisions 0 and 1, and 13.NC-ZJ-201, Revisions lM,as rePorted to the NRC In letter 181 ~01 9, dated June 25, 1991, 'Technical Specification Amendment Request Section 3/4.6.2.2 and Bases.
NRC calculated values as provIdedln tho Safety Evaluation related to amendinents 64, 50, and 37 to PVNGS Units 1, 2, and 3 respectively, dated September 8, 1992.
APS calculation 13-NC-ZY-205, Revision 2.
These LpZvalues were revised In calculation 13-NC-ZY-205, Revision 3, dated February 2, 1996, as a result of tho Inclusion of a previously Inadvertently omitted X/Q value.
Seo APS Letter No. 102%3620r dated March 7r 1996.
GDC 19 requires that the control room dose willnot exceed S rema whole body, or Its equivalent to any part ol the whole body, for the duration ol an scddent.
The 00 rem beta skin dose limitshown here h based on the Suldance of Secthn 6 4 of the Standard Review phn, NUREG0800, Revision 2, July 1981. Thb value appears to have been derived from the okl 10 CFR 2L101 occupational skin limitof 7% rema per quarter.
However, the new occupathnal skin dose limit,from 10 CFR 20.1201, effective January 1, 1994, has been Increased to 50 rema per year.
Table 2-1 (Page 1 of 3): COMPARISON OF POST-ACCIDENT DOSES (Thyroid)
AREAJ CONTRIBUTOR PREVIOUS ANALYSISVALUE'(rem)
(Secondary Side Pressurized)
NEW VALUE(rem)
(Secondary Side Depressurized)
Exclusion Area Boundary (2-hour consequence)
Power access purge 2.3 Containment, leakage (Primary & Secondary) 77 115.5 Recirculation leakage and leakage to RWT TOtal (10 CFR 100 Criteria 300 rcm)
Low Population Zone (30-day consequence) 0.12 80 15b 132.8 Power access purge Containment leakage 0.4104.2'.4 155.8'ecirculation leakage and leakage to RWT TOtal (10 CFR 100 Criteria 300 rem)
Control Room (30-day consequence) 0.28 30 3b 186 Sc Containment leakage (Primary & Secondary) 7.0 14.7 Recirculation leakage and leakage from RWT TOtal (10 CFR 50 GDC 19 criteria 30 rem) 2.6 (-2) 7.0 2.5b 17.2 APS calculations 13NC ZY 205, Revisions 0 and 1, and 13NC ZJ 201, Revisions 0 3, as reported to the NRC in Letter No. 161.04019, dated June 25, 1991, rechnical Specification Amendmcnt Request Section 3/4.6.2.2 and Bases."
Includes NRC Information Notice 91-56 Contribution.
'lhc LPZ values werc revised in calculation 13.NC-ZY-205, Revision 3, dated February 2, 1996, as a result of the inclusion of a previously inadvertently omitted X/Q value.
See APS Letter No. 10243620, dated March 7, 1996.
Table 2-1 (Page 2 of 3): COMPARISON OF POST-ACCIDENT DOSES (Whole Body)
AREA/CONTRIBUTOR PREVIOUS ANALYSIS VALUE*(rem)
NEW VALUE(rem)
(Secondary Side Depressurized)
Exclusion Area Boundary (2-hour consequence)
Power access purge Containment, leakage (Primary & Secondary) 2.2(-3) 2.45 2.2(-3)
Recirculation leakage and leakage to RWT Total (lo cFR 100 critcria 25 rem)
Low Population Zone (30-day consequence) 2.7(-4) 2.5 03 3.98 Power access purge Containment leakage 3.6(-4)1.02'.6(-4) 1.5'ecirculation leakage and leakage to RWT TOtal (10 CFR 100 Criteria 25 rem)
Control Room (30-day consequence) 2.4(-4) 1.0 3.0E-4b 1.5'ontainment leakage (Primary & Secondary) 0.945 1.47 Recirculation leakage and leakage from RWT TOtal (10 CFR 50 GDC 19 criteria 5 rem) 7.9(-7) 0.95 1.5E-3b 1.472 AFS calculations 13 NC ZY 205, Revisions 0 and 1, and 13 NC ZJ 201, Revisions 0 3, as rcportcd to thc NRC in Letter No. 16144019, dated June 25, 1991, rechnical Specification Amcndmcnt Request Section 3/4.6.2.2 and Bases.
Includes NRC Information Notice 91-56 Contribution.
'lhc LPZ values werc revised in calculation 13-NC-ZY-205, Revision 3, dated February 2, 1996, as a result of the indusion of a previously inadvertently omitted XQ value.
See APS Letter No. 10243620, dated March 7, 1996.
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e PVNGS UPDATED FSAR DECREASE ZN REACTOR COOLANT INVENTORY Table 15.6.5-2 RADXOLOG1CAL CONSEQUENCES OF A LARGE BREAK LOCA Dose Exclusion area boundary 2-hour consequence Power access purge Containment leakage and secondary release Recirculation leakag
(~>
Total Thyroid Dose (rem) 2.3 Izz.'B~
Whole Body Dose (rem) 2.2 x 10 C'3 0.3 3.98 Beta Skin Dose (rem)
Low population zone 30-day consequence e
Power access purge Containment leakage and secondary release Recirculation leakage@-l Total
/8b 5 CQ 0.
4'S.
g 3.6 x 10-4
- 3. o x 10-4 Control room, 30-day consequence(>)
Containment leakage and secondary release.
Recirculation jeakag~(e)
Total l7. 2-
/.V.7 l.97>
Z9.4 7'.7 x 10-6 Z9. b7 a.
Assumes no credit for non-ESF filtration or for spray removal of particulates or organic iodines.
b.
Direct dose from fission products in containment atmosphere is less than 0.05 rem, neglecting credit for sprays.
C,. Co<krib~*on.frbM ZN 9 I Sk to~(Ukeh.
March 1994 15.6-73 (2)
Revision 6
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