ML20195C642
| ML20195C642 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/16/1998 |
| From: | STONE & WEBSTER ENGINEERING CORP. |
| To: | |
| Shared Package | |
| ML20195C634 | List: |
| References | |
| UR(B)-456, UR(B)-456-R01, UR(B)-456-R1, NUDOCS 9811170187 | |
| Download: ML20195C642 (13) | |
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,/ ST@NE & WE B STER EN GIN EERING CO RPOR ATION 3
CALCULATION CHANGE NOTICE 4 (SEE INSTRUCTIONS) CIJENT & PROJECT PAGE 1 OF 6 plus 7 pp of Anschments DLC / BVPS Unit 1 CA!fULATION Trrli(Indicative of the ObjectNe): QACATEGORY(/) Combined BVI-BV2 Control Room Doses Due to Waste Gas System Line tirl NuclearSafetyRelated Rupture Accident at BV1 o n o m o NNS , OTitER l CAlfUIATION IDENTIFICATION NUMBER Calc Calculation ' R, CURRENT OITONAL No. Change Notice No. J.O.NO. DIVISION & OROUP CAIL 3. T ASK CODE 12241/14110.39 UR(B) 456 N/A I CCN.I APPROVA13 -SIONATURE & DATE ADMINISTRATIVE PREPARER (SyDATE(S) REVIEWER (S)DATE(S) INDEPENDE?fr CllANGE ONLY REVIEWER (SyDA'IT4S) YES NO Y / ./g - y STATEMENT OF CHANGE
.s 1; Corrected an error in the cxponent of the total control room beta doses reported in Table 17 (p 71) and Tab!c 18 (p 74) for the Waste Gas Line Rupture. .
- 2. Re-ran the Waste Gas System Line Rupture computer model to address the following changes.
Use of new atmospheric dispersion factors based on Ramsdell methodology (instead of the previously used values which are based on Murphy & Campe methodology) It is assumed that the control room bottled air / emergency ventilation system is not initiated by the event. REASON FOR CHANGE
- 1. To correct the estimated total control room beta dose following a WG line rupture event reported on pp 71 and 74 of UR(B)-
456-1,
- 2. To utilize the new atmospheric dispersion factors and demonstrate that Control room habitability can be maintained following a WG line rupture without taking credit for the initiation of the CR emergency bottled airh entilation system.
CONFIRMATION REQUIRED (/) (THIS CCN ONLY) YES O NO SEE PAGE CONFIRMATION REQUIRED. (/) (STATUS FOR CALC & CCNs) YES O NO[ DISTRIBUTION COPY COPY GROUP NAME & LOCATION SENT- GROUP NAME & LOCATION SENT (CC/RO) (CC/RO) RECORDS MGT. Records Retention cc ' FILES (OR FIRE FILEIF NONE) DLC(ILebda) orig NT&L Div
, (SRFerguson 245/7) cc l 9811170187 981109 PDR ADOCK 05000334 P PDR CALC.SLS l
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ __ i
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. ' STONE & WEBSTER bNGINEERING dbRPORATION
, 45010.s5 CALCULATION SHEET
. CALCULATION IDENTIFICATION NWBER I
J.O.OR W.O.NO. DMSlON & GROUP CALCULATION NO. OPTIONALTASK CODE PAGE 2 12241 /14110.30 UR(B) 456-1, CCN1 N/A l TABLE OF CONTENTS I Section Page #- 1 Title Page 1 ) Table of Contents 2 l objective 3 Data 3 Assumptions 3 Computer Program Ident./ Comp. Run Summary List 3 . l Methodology 4 l 1 Calculation 4 Results 6 Conclusion 6 ) References 6
' Attachments Attachment A 2 pages Attachment B 5 pages )
i i
, STONE & WEBSTER ENGINEERING CORPORATION 15010.65 CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER J.O.OR W.o.No. DMSloN & GROUP CALCULATION NO. OPTIONAL TASK CODE PAGE 3 12241 /14110.39 UR(B) 456-1, CCN1 N/A OBJECTIVE
- 1. To correct an error (in the exponent) in the estimated total control room beta dose following a WG line rupture event reported on pp 71 and 74 of UR(B)-456-1. These doses represent the use of atmospheric dispersion factors based, on Murphy and Campe methodology and take credit for post accident control room isolation via automatic action from the contr'ol room radiation monitors.
- 2. To utilize new atmospheric dispersion factors (based on Ramsdell methodology) and demonstrate that Control room habitability can be maintained following a WG line rupture without taking credit for the initiation of the CR emergency bottled air / ventilation system.
DATA Except as noted below, all data used in this analysis is same as that documented for the Waste Gas Line Rupture analysis documentad in Reference 1:
- 1. Accident Atmospheric Dispersion Factors Cor. trol Room Atmospheric Dispersion Factors for releases from the Auxiliary Building: (Reference 2) 0-8 hrs =
4.30E-3 sec/m' l l ASSUMPTIONS
- 1. It is conservatively assumed that the control room radiation monitors will not initiate the CR emergency bottled air / ventilation system. Consequently, the control room is assumed to remain in the normal operation mode, i.e.. utilizing a normal unfiltered intake of 500 cfm for the duration of the accident.
COMPUTER PROGRAM IDENTIFICATION & COMPUTER RUN
SUMMARY
LIST l l Descrintion Job No Date ! DRAGON, V05 LOO 4921 1/16/98 Identification of Computer Hardware l IBM main frame l t i
, STONE & WEBSTER ENblNEERING CORPORATION 45010.65 CALCULATION SHEET
. CALCULATION IDENTIFICATION NUMBER I J.o.OR W.o.NO. DMSION & GROUP CALCULATION NO. OPTIONAL TASK CODE PAGE 4 12241 /14110.39 UR(B) 456-1, CCN1 N/A METHODOLOGY
- 1. A copy of p 71 and 74 of Reference 1, annotated with the corrected beta dose values are included as Attachment 1 of this CCN. These corrected values are also reported ~in the
! in the results section of this CCN.
- 2. Except as noted below, the computer model for the WG line rupture remains the same as documented in Reference 1, i.e., two sources are considered. The first source is a 1 hour release from the ruptured line, and the second source j is a puff release from the charcoal delay beds.
i New atmospheric dispersion factors as documented in datum 1 The control room is assumed to be in the normal ! operation mode for the duration of the accident. i CALCULATION , l SWEC computer code DRAGON (Reference 3) is used to estimate the i gamma and beta doses in control room following a waste gas line rupture at BVPS 1. The model used is identical to that documented in Reference 1 with the exception that new atmospheric dispersion factors are used and no credit is taken for the Control room emergency bottled air / ventilation intake system. A copy of the DRAGON input is provided in the following page. I l 1 l l l
- _. . . .. . = . - . . .. . . - . . -
STONE & WEBSTER ENGINEERING CORPORATION csoio.as CALCULATION SHEET 4.
. CALCULATION IDENTIFICATION NUMBER J.O.OR W.O.NO. DMSION & GROUP CALCULATION NO. OPTIONAL TASK CODE PAGE 5 12241 /14110.30 UR(B) 456-1, CCN1 N/A l
***** PROGRAM - DRAGON -- NU115.VER05. LEV 00-- 4/30/86 ***** i
* * * * * * * *
- CARD IMAGE OF INPUT SUBMITTED TO DRAGON *********
CARD COLUMNS 1 2 3 4 5 6 7 8 12345678901234567890123456789012345678901234567890123456789012345678901234567890 CARD No. 1 ** CONTROL ROOM DOSE, BV1 GWS RUPTURE, 1A, RELEASE FROM LINE, NO ISOL. 2 8 11 011 1.0 1.0 120. C 3 GWS PIPE 2.50+5 4 CONTROL ROOM 1.73+5 10. 1.0-3 5 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.C"0 i 6 0.00E0 0.00E0 0.00E0 0.00E0 1.90E0 1.06E1 1.20E0 3.10Eu l 7 0.00E0 0.00E0 3.00E0 2.60E1 1.10E0 3.10E0 0.00E0 6.3E-1 8 1. 1.0 { 1 50 50 4.30 1.0 .20 i 9 2 1. 1.0 50 50 4.30 1.0 .50 i 10 3 1. 1.0 50 50 4.30 1.0 1.0 I 11 4 0. 1.0 50 50 4.30 1.0 1.50 12 5 0, 1.0 50 50 4.30 1.0 8 13 6 0. 1.0 50 50 1 1.0 24 14 7 0. 1.0 50 50 1 1.0 96. 15 8 0. 1.0 50 50 1 1.0 720.
.16 ** CONTROL ROOM DOSE, BV1 GWS RUPTURE,18, RELEASE FROM DELAY BED, NO 150.
17 8 11 011 1.0 1.0 18 CHARCOAL BED 2.50+5 19 CONTROL ROOM 1.73+5 10. 1.0-3 - 20 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 I 21 0.00E0 0.00E0 0.00E0 0.00E0 3.03E0 1.06E2 3.77-4 8.29-1 l 22 0.00E0 0.00E0 1.45+1 6.58+1 0.0E0 1.80E1 0.00E0 0.0E00 1.0 1 23 1 50 50 4.30 1.0 .20 24 2 1.0 50 50 4.30 1.0 .50 25 3 1.0 50 50 4.30 1.0 1.0 26 4 1.0 50 50 4.30 1.0 1.50 27 5 1.0 50 50 4.30 1.0 8. 28 6 1.0 50 50 1 1.0 24. 29 7 1.0 50 50 1 1.0 96. 30 8 0. 1.0 50 50 1 1.0 720. 12345678901234567890123456789012345678901234567890123456789012345678901234567890 l i I i l i ) 1
, . - . _ - . - . - .- . . ~ - . . ~ - . . - - - - - . - - - - - - -
STONE & WEBSTER ENGINEERING CORPORATION csoio.ss CALCULATION SHEET.
. CALCULATION IDENTIFICATION NUMBER J.O.OR W.O.NO. DMSION & GROUP CALCULATION NO. oPTIONALTASK CODE PAGE 6 12241114110.30 UR(8) 4561, CCN1 N/A ,
RESULTE
- 1. Tra control room doses following a Waste gas line rupture based on use of Murphy and Campe atmospheric dispersion 1 factors and taking credit for post-accident control room isolation via automatic action due to a signal from the CR, radiation monitors are as reported in Attachment 1 and repeated below:
Source Gamma (Remi Beta (Rem) i Line Release 2.54E-03 7.77E-02 Charcoal Delay Bed 5.77E-04 5.42E-02 Total 3.1E-03 1.3E-01
- 2. The control room doses using new atmospheric dispersion factors (based on Ramsdell methodology) without taking credit for the initiation of the CR emergency bottled air / ventilation system is as follows:.
Source Gamma (Remi Beta (Rem) Line Release 6.05E-03 2.05E-01 Charcoal Delay Bed 3.87E-04 3.84E-02 Total 6.4E-03 2.4E-01 CONCLUSION
-Based on the - above it is concluded that using the Ramsdell X/Q's, the BVPS control room doses following a BV1 waste gas line rupture, remains well within the dose requirements of 10CFR50, GDC 19 (i.e. 5 Rem Gamma and its equivalent, 30 Rem beta) even when no credit is taken for the initiation of the control room emergency ventilation system.
REFERENCES
- 1. SWEC Calc 12241/14 410. 39-UR(B) -4 56-1, " Combined BV1/BV2 CR l
Habitability due to Design Basis Accidents (except LOCA) at BV1" !- 2. NUS ltr ARP-91-444, dated Oct 8, 1991 "CR X/Q values for BVPS" (sent via fax by' JLebda (DLC) dated 1/15/98) - Attachment 2
- 3. SWEC Computer Code DRAGON, NU115, Version 05, Level 00
- 4. 10 CFR Part 50, Appendix A, GDC 19, " Control Room" b
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b M r\ h h k-{ l l 12241/14110.39 48/84 UR(B)-456-0 N.) 71 i CCMi . Catc s2 t.41/ t9.uo, act- uR6,)- @-\ , CAM \ TABLE 17 [ - . 1 j BVPS1 UASTE OAS SYSTEM RUPIURE 1 CONTROL ROOM DOSES 30-day INTEORATED DOSE (REMI
- i Activity thyroid samma' beta l sou'rce l l
LINE RUPTURE
- a. Line break --- 2.54-03 7.77-02
- b. Delay Bed --- 5.77-04 5.42-02 g ,g ,
- 1 V '
\
TOTAL --- 3.1-03 (1.3-0M \-3-0) I TANK RUPTURE --- 7.07-04 1.26 a R2693D45 Js3087 4/22/87 t- ! NOTE: For LINE RUPTURE: Control Room isolation for 1 hour by radiation monitor signal - safety limit = 1 arem/hr samma 0 l l l' i l
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t 4 -: TABLE 18 (Cont.) BV1 DESIGN BASIS ACCIDENTS CONTROL ROOM DOSES -
SUMMARY
(30-day Integrated Dose) DOSE (Rem) Postulated ---------"-------------- Calculation Accident Thyroid Gamma Beta Section Reference _ _ _ _ _ . . . . . . . . _ . _ _ _ _ _ _ .. . _ _ _ _ _ . = - - - - _ - _ .. Steam Generator Tube V Rupture (3),(2) pI-Spike 3.2 2.1-3 7.4-2 Table 13 cI-Spike 1.9 2.3-3 7.6-2 Table 14 Locked Rotor Accident (4) 5.7 3.5-4 5.0-3 VI Table 15 Loss of AC Power (4) 0.8 7.1-5 2.7-3 VI Table 15 Waste Oas System Rupture I'3'k VII Table 17 C.CtJ \ Line Rupture (1) --- 3.1-3 1 Tank Rupture (4) --- 7.1-4 1.3 1 1 i i (1) Isolation by area radiation monitor signal based on a setpoint with i safety limit dose rate of 1 mram/hr gamma in the control room. (2) Purge of control room atmosphere for a minimum of 30 minutes at 33,000 cfm at t=8 hr post-accident initiation or at indicated time. (3) Isolation by manumi operator action at t=30 min post-secident intiation. (4) No action required. 1 l I l' . l.
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DUQUESNEi10HT00 l 6RE E LA- ' BVPS-ERF P.O.80X4 F =' RGas o N SHIPPlH0 PORT,PA j 15077 .. Phono . FsxPhone Phone 412-393-5521 CC: FatPhuse 412-393-5621-l 2 i REMARKS: Ument Foryourreview ' Reply ASAP Pleaso Comment I + 48W .
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? .w,:<.... I n.s.: :.. :% ARP-91-444 October 8, 1991 l Hr. Steve La vie l Duquesne Light company Beaver Valley Power Station P. O. Box 4 shippingport, PA 15077 Subjects control Room X/Q Values for BVPS
References:
- 1) HALLIBURTON NUS Proposal No. P8808127 -
. 2) Duquesne Light Company Purchase order No.
' D068239
- 3) Telecon From S. La Vie to H. Septoff August 9, 1991
- 4) Letter from J. Ramsdell to H. Septoff August 15, 1991 ~
! Dear Steve This letter presents the X/Q values suitable for design basis accident releases from selected plant vents to the BVPS common control room intake. The methodology used is presented by Ramsdell in NUREG/CR-5055 as modified by NUREG/CP-0116, by discussions with
- Ramsdell in September 1991 (Reference 4) and a paper presented in Atmospheric Environment, volume 248, No. 3, pp 377-388, 1990. The work was performed in accordance with the descriptlen contained in Reference 3 as approved by reference 2. It is noted that all work was performed using approved project procedurcs in accordance with l the HALLIBURTON NUS E5D Quality Assurance Manual, Revision 6.
Tables 1 and 2 presents the X/Q values for the selected plant vents
- for Unit 1 and Unit 2, respectively, for averaging periods of 0-8 t hours, 8-24 hours, 1-4 days, and 4-30 days. The release points, distances and directions to the common control room intake, and building cross sectional areas were those provided in an analysis performed by Stone and Webster corporation using the Murphy and campe methodology. Duquesne Light Company provided this information to us on September 6, 1991. Five years of' meteorological data for the period January 1986 through December 1990 were used. Results of the Nurphy and campe methodology-are also presented in the tables for comparison. It is seen that, for l the 0-8 hr averaging period reductions in X/Q values as compared to ,
those obtained using the Murphy and campe nethodology range from a factor of 2 to over an order cY-magnitude. ( r 4 In Imr.lo;tc.s sm.! serris c., jo.c so cleuroter .r ust ssster u * **l.l 9 e
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giv m uesne E R S-MPp- @l-{}35 , I %F D Heam enyus oeow ATTACHMENT LL Page $T of $$ l Mr. Steve La Via ARP-91-444 October 8, 1991 page 2 t I A report describing the methodology and results with a comparison I with the Murphy and campe methodology ' suitable for presentation to the NRC will be prepared. The computer cede and its documentation will be provided with the report. Further, as we discussed, a scientific paper could also be prepared suitable for presentation at a DOE /NRC Nuclear Air Cleaning Conference. As part of MALLIBURTON NUS Quality Assurance procedures a Division Quality Assurance Review Board (0QARB) was convened to review the technical and quality aspects of the analysis. The results of the DQARB indicate that (1) the documentation for the computer code , generated for the analysis should be revised to provide additional ' information related to code identification and its use, and (2) the *
- need to clarify the relationship between the test cases and the ,
[ hand calculations used to verify the correct operation of the code. ' l Therefore, the results provided in the tables should be considered as preliminary until the DQARB approves the documentation, receives l the clarification, and completes its review. It is expected that j this vill be completed early next week. If you have any questions please call me. 1 ! Sincerely, L l . Michas Septoff Project Manager Enclosures cc: A. Toblin
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MeL1h PftyM3 040&*J-et ATTACHMENT L Page $ of 5/o TABLE 1 DESIGN B ASIS ACCIDENT X/Q VALUE5 (sec/m3) FOR SELECTEC 3VPS PLANT VENTS To THE COMMON CCHTROL ROOM IHTAKE - UNIT 1 Release Point Hethodology 0-8 hr 8-24 hr 1-4 day 4-30 day Containment Ramsdell 4.33E-4 2.04E-4 1.46E-4 8.84E-5 Edge Murphy-Campe 2.88E-3 1.90E-3 6.62E-4 1.41E-4 Containment Ramsdell 2.73E-4 1. 2 8 E-4 9.17E-5 5.57E-5 , Top Harphy-Campe 2.51E-3 1.66E-3 5.77E-4 1.23E-4
]
Auxiliary Ramsdell 4.30E-3 2.01E-3 1.49E-3 9.25E-4 ) Building Hurphy-Campe 8.24E-3 6.01E-3 2.32E-3 6.18E-4 ; Main Ramsdell 7.60E-4 3.51E-4 2.59E-4 1.58E-4 l Stearvalve Murphy-Campe 2.97E-3 1.94E-3 6.92E-4 1.54E-4 j Service . Ramsdell 6.25E-4 3.04E-4 2.36E-4 1.57E-4 ' Building Hurphy-Campe 7.47E-3 5.09E-3 1.88E-3 4.93E-4 ) Turbine Ramsdell 2.43E-3 1.22E-3 8.90E-4 6.26E-4 ) Building Harphy-Campe 7.81E-3 5.55E-3 2.11E-3 7.11E-4 I cas Waste Ramsdell 5.11E-4 2.15E-4 1.65E-4 1.14E-4 Storage Hurphy-Campe 2.03E-2 1.51E-2 5.99E-3 1.32E-3 Vault 9 HALUBURTON .%'S p I toog .in3n as'sano.la Iv3 oc:t1 nal 96/ST/10
C.sd c. \u.s t lssno n- u(UG IVR-\, teu \ g fD b-[ Amu & a ccd] . sM.guesne ERS-#@ 9 l-035 Nav enyscs ceca **1 ATTACHMENT age [ h of % TABLE 2 DESIGN BASIS ACCIDENT X/Q VALUES (sec/n3) FOR SELECTED BVPS PLANT VENTS TO THE COMMON CONTROL ROOH INTAKE - UFIT 2 Release Point Methodology 0-8 hr 8-24 hr 1-4 day 4-30 d,ay Containment Ramsdell, 1.88E-4 9.32E-5 7.06E-5 4.18E-5 Edge Murphy-Campe 4.16E-3 2.81E-3 1.09E-3 1.58E-4 Containment Ramsdell 1.20E-4 5.91E-5 4.45E-5 2.64E-5 Top Murphy-Campe 3.65E-3 2.47E-3 9.56E-4 1.39E-4 Auxiliary Ramsdell 1.04E-3 5.15E-4 4.04E-4 2.46E-4 l Building Murphy-Campe 1.33E-2 9.30E-3 3.94E-3 1.20E-3 Main Ramsdell 1.59E-4 7.86E-5 5.96E-5 3.76E-5 Steanvalve Murphy-Campe 7.75E-3 5.63E-3 1.99E-3 3.26E-4 Service
- Ramsdell 2.21L-4 1.11E-4 8.51E-5 5.17E-5
- Building Murphy-Campe 5.42E-3 3.62E-3 1.43E-3 3.31E-4 Turbine Ramsdell 2.72E-4 1.43E-4 1.10E-4 6.30E-5
,_B_u ilding Murphy-Campe 6.46E-3 4.90E-3 2.00E-3 5.75E-4 Cas Waste Ramsdell 1.74E-3 9.36E-4 7.69E-4 5.55E-4 Storage Murphy-Campe 1.23E-1 1.04E-1 5.08E-2 2.00E-2 Vault
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