ML20235W720

Responds to Two Concerns Delineated in Re Offsite Dose Calculation Manual.Util Always Performs Priority LLD Calculation & Compares Results to Tech Spec Table 4.11-2 Requirements to Ensure Compliance

ML20235W720
Person / Time
Site:	Beaver Valley
Issue date:	10/06/1987
From:	Sieber J DUQUESNE LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
TAC-63996, NUDOCS 8710160378
Download: ML20235W720 (9)

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Stuppingport, PA 15077-o004 -

0ctober 6, 1987.

(II'Sh Nucicar Regulatory Commission Attnt'fDocument' Control Desk

. Washington,'DC. 20555 D.; ,;

[ References' -Beaver Valley Power Station, Unit No. 2J .

.BV-2 Docket No. 50-412, License NPF-64' . .

NRC; Letter:RE: J Beaver . Valley Unit 2 . Of fsite Dose Calet.1ation Manual', ODCM (TAC 63996)

- Gentlemen

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This! letter- is, ini response to the two concerns .' delineated .in the '. lette r Ldated, July 7

.14, 1987 -; ( received July 29, 1987) f rom Mr. Peter S. Tam. 'Your 4

concernsJand;our' responses are' described below:

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NRC' Concern 1: ;The note on page 2-8 (regarding noble gas nuclides) should be deleted as. agreed to by your staff.

'DLC Responser~ The note on page 2-8 states: "If the radioactivity of a noble I gas' radionuclides is below the LLD value specified in Table 4.11-2 of the BVPS-2 Technical ' Speci fications ,. the noble gas radionuclides should not be included 'as a source term in this setpoint calculation."

Please note that DLC has always- performed a priori LLD calculations (ie; before using a particular counting instrument-for gaseous waste sample analysis). The results of the LLD calculations are then compared to Technical Specification

-Table 4.11-2 requirements to ensure compliance.

For all applications, any radionuclides identified in a sample

--analysis is used in the setpoint calculation and for dose / dose rate -determinations. This is true even when the sampic concentration is less than the LLD specified in Technical Specification Table 4.11-2.

A change.to this note will be processed as soon as practicable and will be submitted to the NRC with the next Semi-Annual Radioactive Effluent Release Report.

8710160378 871006I '

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Document Control Desk

October 6, 1987 Page Two l

NRC Concern 2,: Pages 2-21'and 2-22 should be revised to require the use of ,

short-term X/Q values in calculating doses from any i containment purge when the value of the T factor (addressed on j pages 2-8 and 2-9) is greater than 1. l DLC-Response: NUREG-0133 (Preparation of Radiological Effluent Technical l Specifications for Nuclear Power Plants) Section 3.3 statts: [

" Determination of doses due to short-term releases can use the l annual average relative concentration (long-term) if it-can be demonstrated.that past short-term releases were sufficiently  !

random in both. time of day and duration - (eg; the short-term -j release periods were- not depender.t. solely on atmospheric- .j conditions or time of day) to be represented by. the annual average dispersion conditions." i Attachment l':to this letter contains. a summary of all l short-term release periods at BVPS Unit 1 since implementation  !

of the Radiological Effluent Technical Specifications on January 1, 1984. From this summary it is evident that past short-tern releases were sufficiently random in both time of l day'and duration. ,

j lt should also be noted that although the ODCM permits-use of ,

long-term X/Q's for dose determination, it does specify the f more restrictive short-term X/Q's for effluent mcnitor  ;

i setpoint_ determination. The actual discharge procedure for containment purges also uses a conservative 60% criteria in the effluent monitor setpoint calculation (ie; an upper alarm indicates 60% of the most restrictive 500 mrem /yr Total Body Dose Rate or 3000 mrem /yr Skin Dose Rate).

i verses I UsingtheNRCimposedshort-termX/gof(allowed 3.32E-4bysec/m3 the long-term X/Q of 1.03E-4 sec/m NUREG 0133')

would increase the resultant short-term doses.and dose rate by .I a factor of 3.22. Consequently, this would require the use of the NRC allowed T factor sooner than was originally intended.

] i For example, the T factor was intended for use when J instantaneous maximum noble gas Total Body Dose Rates exceed 500 mrem /yr. The T factor permits the averaging of the noble gas Total Body Dose Rate for up to 960 minutes when performing ]

Containment Purges. Thus, implementation of the NRC imposed f short-term X/Q would require use of the T factor when noble gas Total Body Dose Rates exceed 155 mrem /yr (using the same noble gas concentrations).

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f I,'4' ' - Document Control Desk October 6, 1987 Page Three f

In conclusion, use of the NRC imposed short-term X/Q would not give us the operational flexibility allowed by 10CFR50.36a, 10CFR50 Appendix 1 Section IV, 10CFR50 Statements of Consideration (35 FR 18385) and NUREG-0133 Section 3.3. We believe that the data included as attachment 1 of this letter demonstrates that discharges from BV-Unit 1 (and therefore would be representative of Unit 2 discharges) have been l sufficiently random as to satisfy the provision in Section 3.3 l of NUREG 0133 which would permit the use of long term X/Q for short-term releases. Therefore, Duquesne Light Company request s that the NRC review the data submitted herewith to determine the appropriateness of our conclusion.

Very truly yours, q

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J. D. N~ieEe r Vice President Nuclear Attachment cc Mr. Jim Beal, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 Mr. Stephen M. Pindale , Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulat ory Commission Regional Administrator Region 1 631 Park Avenue King of Prussia, PA 19406 Mr. Pet er S. Tam U. S. Nuclear Regulatory Commission Project Directorate 1-4 Division of Reactor Projects I/II Washington, DC 20555 Director, Safety Evaluatton & Control Virginia Electric & Power Company P.O. Box 26666 One James River Plaza Richmond, VA 23261 l

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S'ummat. ion of BVPS-I' Past Short-Term Release Periods i.

1984 (1).

Discharge Total Diccharge

. Discharge Start ' E l eva t. i on Duration.

Permit No. 'Date Time (Feet)' (Minutes) 1/4 0400 150

• 30 669 1707 500 1071

!. 670 1/10 3 671 1/13 0658 500 718- )

6721 'l/10 0600- 100* 227 1815 500, ,741 673 -3/8 3/9 0912 500 764 .i 674_

675 3/10 1815 500 886 676- 3/16 2008 100 330' 677- 3/22 2032- 500 748 678 3/29 0941' 500 '774 679 4/7 2105 500 655 682 4/17' '1950 500 697 .

683 5/15 1730 100* 30 1958 150 9 683 '5/15 -

683 5/15 2100 150 27 684 5/31 0350 500. .921.

500 727

.685 -6/12 1228' 686- 6/14 0530 500 935 687 , 7/10 1430 150* 30-688 7/20. 2!00 500' 570 689 7/21 0640 500 785 690 8/20 1238 500 887 1010 500 701 691 9/2 500 5,78 692 9/3 1322 693 .9/4 1400 500 963 694 9/5 0920 500 300 694 9/5 1436 500 609 1 106 l 695 9/8 1837 500 696 9/7 1655 150* 325 697 9/11 2038 500 847 698' 9/12 0345 500 684 699 9/20 1709 500 840 700 '9/29 1836 500 611 (1). 500 foot releases consist of batch ventings of Gaseous Waste Decay Tanks (except t hose denoted by an asterick) 100 foot releases consist of batch purges of the Reactor Containment Atmosphere (except those denoted by an asterick)  ;

100, 150 and 500 foot releases denoted by an asterick (*) are for batch quantifications of Abnormal Releases through the gaseous  ;

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ATTACliMENT 1 Summation of~BVPS-1 Past Short-Term Release Periods f

1984 Continued (1)

Discharge Total Discharge Discharge Start Elevation- Duration Permit No. . Date Time (Feet) (Minutes)

\;. 702 10/12 1455 500 401 703 10/12 2140 500 762 704 10/13 1656 500 720

'705 10/14 2124 500 739 706 10/14 0514 100 967 707- 10/15 1217 '500 609-708. 10/15 2235 S00 905 709- 10/16 1508' 500 940 4 710 10/17 1717 500 413 710 10/18 0119 500 437 711 .10/18 0955 500 1062

- 712 10/19 1225 500, 984 713 10/21 1033 500 939 714' 10/22 0653 500 1042 715 .10/24 0957 500 895 716 11/14 2020 100 974

'717; .12/19 0404 500 626 718 12/20 1413 500 1062 719- 12/22 1719 100 91 719! 12/23 0930 100 180 720 12/22 2027 500 735 771 12/23 1545 500 714 722 12/24 0920 500 1255

.723 12/25 1600 500 990 724 12/26 0903 500 1410 725- 12/27 0915 100 77 726 12/29 1905 500 792 727 12/30 0820 500 965 (1) 500 foot releases consist of batch ventings of Gaseous Waste Decay Tankr, (except those denoted by an asterick) 100 foot releases consist of batch purges of the Reactor Containment Atmosphere (except those denoted by an asterick) 100, 150 and 500 foot releases denot ed by an ast erick (*) are for batch quantificat ions of Abnormal Releases t brough t he gaseous effluent monitors

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Summation of,.BVPS-1 Past.Short-Term Release Periods 8 w ,

,b' t 1985 (1)

Discharge Total Discharge Discharge Start,, Elevation Duration Permit No. Date Time (Fece) (Minutes)

'728 1/1' 1328 500 L528 729' 1/2 2005 500 930 730 1/8 1108- 500 e 120

730. 1/8 1340 500 820 731 3/17 0640 500- 92 731 -3/17 1205 500 570 732 3/16 1837 100* 53 733 3/29 1055 500 770 734 4/26 1315 500 501 735 4/26 2258 500 g u 445 736 4/27 1745 500  % 707 737 4/28 1014 500 1056-738 '4/29 0628 500 788 739 4/29 2215. 500 892 i 895  !

740 4/30 1325 500 742 i 5/1 0525 500 '

1020 743 5/3 0050 500 305 743' 5/3 0910 500 156 743 5/4 0047 500 529 744 / 5/3 1220 100 290 745 5/5- 1153 500 1157 746 4 5/7 2350 500 1223 747 5/21 2002 500 1090 748 5/31 1100 100 *' 40 ,I 749 6/3 1834 500 1026 750 ,

6/7 1407 500 853 .

217 I 751 7/12 L834 . 500 751 7/13 1404 500 920 752 . 8/2 1613 500 370 752 8/3 011rv 500 73 752

,d/3 0430 500 122 753 8/31 1455 500 45 753 8/31 1841 500 644 754 8/31 .1510 100* 25

" 500 1216 756 9/10 0718 757 10/14 1700 500 517 758 11/21 1.155 500* 45 759 11/29 1200 500* 40

.760 12/27 1448 100* 1 (1) 500 foot releases consist of batch ventings of Gaseous Waste Decay Tanks (except those denoted by an asterick) 100 fu t releases consist of batch purges of the React or Containment Atmosphere (except t hose denot ed by an ast erick) 100, 150 and 500 foot. releases denoted by an asterick(*) are for batch quantif1 cations of Abnormal Relaases through the gaseous effluent moni t ors l

f ATTACHMENT 1 j;

Summation of BVPS-1 Past Short-Term Release Periods 1986 (1)

Discharge Total Discharge Discharge Start Elevation Duration

' Permit No. Date- Time (Feet) (Minutes) _

761 1/6' -1757 500 810 0859 500 44 l 761 1/7 762- 1/23 1050 500 577 763 2/6 1005 500 485 764 2/14 1710 500 530 765 2/20' 0230 500 570>

766 '3/10 1900 500 450 '

767 3/22 1720 500 569 768 3/30 1230 500

• 30 769 4/4 1406 500 34 773 4/8 1431 500 1 774 4/9 '2240 500 694 775 4/11 1510 500 8 776 4/1'2 1717 500 467 777 4/15 1052 500 464 778 4/22 1745 100* 60 780 .5/11- 1829 100* 2 781 5/11 1829 150* 2 785 .5/17 1600 500 368

.786 5/18 0228 500 607 787 5/18 1322 500 467 788 5/18 2307 100 1027 789 5/19 1635- 500 441 790 5/20 0041 500 49 790 5/20 0344 500 340 791 5/19 2230 100

• 180 792 5/20 1007 500 536 793 5/20 2007 500 458 794 5/21 0350 500 994 795 5/22 0525 500 985 796 5/23 1213 500 1009 797 5/24 0535 500 1030

.798 5/26 1710 500 1117 799 5/27 1233 500 1032 800 5/28 0630 500 170 800 5/28 0940 500 748 801 5/30 1704 500 1 802 5/31 1401 500 599 802 6/1 0000 500 502 (1) .500 foot releases consist of batch ventings of Gaseous Waste Decay Tanks (except those denoted by an asterick) 100 foot releases consist of batch purges of the Reactor Containment Atmosphere (except those denoted by an asterick) 100, 150 and 500 foot releases denoted by an asterick(*) are for batch quantificat. ions of Abnormal Releases t hrough the gaseous effluent monitors

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. . . . -i Sumniation of BVPS-1 Par,t Short-Term Release Periods

'1986 Continued'

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Discharge Total discharge.

Discharge Start Elevation Du ra t ion ..

. Permit No. Date -Time (Feet) (Minutes) f 1 805 8/1= 1351. 500- 865 807 8/2 1442 500 708 808 8/3 0234' 100 558 809 8/4 .0145 500 1145 810- 8/11 0712' 100 278 811 '8/9 0054 500 819

'812' 8/9 '1706 500 '1023 813 8/10 1440 500 930 814 8/14 0954 500 126 814 8/14 1300- 500 903 815 8/15 0845 500 1080

'816 8/16 0400 500 525 816 8/16 1324 500 32 816 8/16 2110 500 390

817 8/17 0404 500 964 818 8/18 0351 50.0 203 818 8/18 0911 500 525 819 8/18 1855 500 960 820 8/21 1954 100 256 821. 8/22 0400 500 35 821 8/22 0445 500 861 822 8/23 0140 500 2 822 8/23 1642 500 718 823 8/24 1432 500 906

.824 8/27 1332 500 807 825 11/9 1015 500 1080 826 11/10 1439 500 952 827 11/19 1305 500 1030 828 11/24 1154 500 528 828 11/24 2145 500 436 829 11/28 1352 500 900

-(1) 500 foot releases consist of batch ventings of Gaseous Waste Decay Tanks (except those denoted by an asterick) 100 foot releases consist of batch purges of the Reactor Containment Atmosphere (except t hose denoted by an asterick) 100, 150 and 500 foot releases denoted by an asterick(*) are for batch p quantifications of Abnormal Releases through the gaseous l effluent monitors

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Summation of BVPS-1 Past Short-Term Release' Periods 1987 (1) .

Discharge Total Discharge Discharge' Start Elevation Duration Permit No. Date- . Time (Feet) (Minutes) 830 .1/3. .0959 100* 3 831- 1/13' 0210 500 955

'0252 500* 20 832 2/14' 832- 2/14 0300 100 45 833 2/27. 0540 500 30 833 2/27 1410 500 1425 834- 3/7_ 1840 500 903 835 3/23 1818 100* 5 836 3/25 0030 500 1090 837 3/28 1614 100* 7 838 4/26 1024 100 962

• - 839 4/28 0230 500 1038 84') 4/28 2022- 500 791 841 4/28 1419 100* 1 842 ~4/29 1838 500 572 843 4/29 0900 100* 240 844 4/30 0420 500 693 845 4/30 2051 500 454 846 5/1 0229 100* 1 847 5/1 '1320 500 131 847 5/1 1547 500 604 848 5/2 0503 500 941 849 5/3 1846 500 829 850 5/2 2220 100 1113 851 5/4 0930- 500 992 852 5/12 1358 100 960.

853 5/13 1300 500 1020 BS4 5/14 0920 500 370 856 5/15 0208 500 827 857 5/15 1840 500 656 857 5/16 1139 500 381 858- 5/16 0605 100 300 .

859 5/20 2218 500 774 860 5/21 1145 100 960 861 5/26 0256 500 1069 862 5/28 1400 100 278 863 6/25 2132 500 1089 864 6/30 1756 500 363 865 6/30 0300 500* 57 (1) 500 foot releases consist of batch ventings of Gascous Waste Decay Tanks (except those denoted by an asterick) 100 foot releases consist of batch purges of the Reactor Containment Atmosphere (except those denoted by an asterick)

100, 150 and 500 foot releases denoted by an asterick(*) are for batch quantifications of Abnormal Releases through the gaseous effluent monitors i