ML20237K405
| ML20237K405 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/30/1987 |
| From: | Barnes W, Harrell E, Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 87-527, NUDOCS 8709040334 | |
| Download: ML20237K405 (77) | |
Text
SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION JANUARY 01, 1987 TO JUNE 30, 1987 PREPARED BY:
dd William C. Barnes, III Assistant Supervisor Health Physics' (Count Room & Environmental)
REVIEWED BY: I A.' H. Stafforf f Superintend M Hea h Physics APPROVED BY:
(
/
/
E. Wayne HErrel
'F-
'7 Station Manage G709040334 870630 PDR ADDCK 05000338 R
pon gtg.g
FORWARD i
This report is submitted as required by Appendix A to Operating License Nos.
NPF-4 and NPF-7, Technical Specifications for North Anna Power Station, Units 1 and 2, Virginia Electric and Power Company, Docket Nos. 50-338, 50-339, Section 6.9.1.9.
l l
l 1
l SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE NORTH ANNA POWER STATION j
JANUARY 01, 1987 TO JUNE 30, 1987 INDEX SECTION NO.
SUBJECT PAGE 1
PURPOSE AND SCOPE.
1 2
DISCUSSION 2
3 SUPPLEMENTAL INFORMATION 3
........... Effluent Release Data 4
................. Annual and Quarterly Doses.
5
.............. Revisions to Offsite Dose Calculation Manual (ODCM) 6
.. Revisions to Process Control Program (PCP) 7
....... Major changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems 8
............. Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation Inoperable.
9
.............. Unplanned Releases.
10
.................. Changes Required By The Land Use Census Evaluation.
11
.. Lower Limits of Detection for Effluent Sample Analysis.
12/13 1
i 1
Page 1 1.0 PURPOSE AND SCOPE The Semi-Annual Radioactive Effluent Release Report includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in' Liquid and Gaseous Effluents of Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. The report also includes a list of unplanned releases during the reporting period.
As required by Technical Specification 6.15.2 changes to the ODCM for the time period covered by this report are included.
Information is provided to support the changes along with a package of those pages sf the ODCM changed.
This report includes changes to the PCP with information and documentation necessary to support the rationale for the changes as required i
by Technical Specification 6.14.1.
This report includes a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Technical Specification 3.12.2.
Major changes to radioactive liquid, gaseous and solid waste treatment systems are reported as required by Technical Specification 6.16.1.
Information to support the reason (s) for the change (s) and a summary of the 10 CFR Part 50.59 evaluation are included.
In lieu of reporting major changes in this report, major changes to the radioactive solid waste treatment system may be submitted as part of the annual FSAR update in accordance to Technical Specification 6.16.
[
Page 2 1.0 PURPOSE AST SCOPE (cont.)
As required by Technical Specification 3.3.3.10.b and 3.3.3. II.b, a list and explanation for the inoperability of radioactive liquid and/or gaseous effluent monitors is provided in this report.
2.0 DISCUSSION The basis for the calevlation of the percent of technical specification for the critical organ in Table 1A is Technical Specification 3.11.2.1.b.
Technical Specification 3.11.2.1.b requires that the dose rate for iodine-131, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days shall be less than or equal to 1500 mrem /yr to the critical organ at and beyond the site boundary. The critical organ is the child's thyroid; inhalation pathway.
The basis for the calculation of percent of technical specification for the total body and skin in Table 1A is Technical Specification 3.11.2.1.a.
Technical Specification 3.11.2.1.a requires that the dose rate for noble gases to areas at or beyond site boundary shall be less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin.
The basis for the calculation of the percent of technical specification l
in Table 2A is Technical Specification 3.11.1.1.
Technical Specification 3.11.1.1 states that the concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B. Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to l
2.0E-4 microcuries/ml.
Percent of technical specification calculations are based on the total
)
gaseous or liquid effluents released for that respective quarter.
Page 3 2.0 DISCUSSION (cont.)
Unplanned releases presented in Attachment 7 are defined according to the criteria prcsented in 10 CFR Part 50.73.
Gaseous unplanned releases are those radioactive releases that exceed 2 times the applicable concentrations of the limits specified in Appendix B, Table II, of 10 CFR Part 20 in unrestricted areas, when averaged over a time period of one hour. Liquid j
unplanned releases are those effluent releases that exceed 2 times the limiting combined Maximum Permissible Concentration (HPC) specified in Appendix B, Table II, of 10 CFR Part 20 in unrestricted areas for all radionuclides except tritium and dissolved noble gases, when averaged over a time period of one hour.
The typical Lower Limit of Detection (L.L.D.) capabilities of the radioactive effluent analysis instrumentation are presented in Attachment 9.
These Lower Limit of Detection values are based upon conservative conditions (i.e., minimum sample volume and maximum delay time prior to analysis).
Actual Lower Limit of Detection values may be lower.
If a radioisotope is not detected when analyzing effluent samples, then the activity of that I
radioisotope wil1 be reported as Not Detectable (N/D) on Attachment 1 of I
~
this report. When the radioisotopes listed on Attachment 1 for a particular quarter and release mode are less than the Lower Limits of Detection, then the totals for this period will be designated as Not Applicable (N/A).
3.0 SUPPLEMENTAL INFORMATION l
There are no inclusions for the time period covered by this report.
Page 4 l
i i
ATTACHMENT 1 i
i EFFLUENT RELEASE DATA (1/87 - 6/87)
This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste, as outlined in Regulatory Guide 1.21.
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TABLE 3 NORTH ANNA POWER STATION SEMI-ANNUAL RADI0 ACTIVE EFFLUENT PELEASE REPORT I
SUMMATION OF SOLID RADI0 ACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS FOR 01-01-87 THROUGH 06-30-87 j
A.
SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-MONTH ESTIMATED TOTAL 1.
Type of Waste UNIT PERIOD PERCENT ERROR (%)
1 a.
Spent resins, filter sludges, m3 9.46E+1 2.50E+1 evaporator bottoms, etc.
Ci 3.15E+2 2.50E+1 l
b.
Dry compressible waste, ma 1.40E+2*
2.50E+1 contaminated equipment, etc.
Ci 7.42E+0 2.50E+1 i
I c.
Irradiated components, control m3 0.00E+0 0.00E+0 rods, etc.
Ci 0.00E+0 0.00E+0 d.
Other (describe) m3 0.00E+0 0.00E+0 Ci 0.00E+0 0.00E+0 2.
Estimate of major nuclide composition (by type of waste)
- a. Iron - 55 1.38E+0 2.5 E+1 Cobalt - 58 1.58E+0 2.5 E+1 Cobalt - 60 6.51E+1 2.5 E+1 Nickel - 63 1.67E+1 2.5 E+1 Cesium - 134 3.84E+0 2.5 E+1 Cesium - 137 1.09E+1 2.5 E+1
- b. Chromium - 51 3.31E+0 2.5 E+1 Manganese - 54 3.04E+0 2.5 E+1 Iron - 55 2.02E+1 2.5 E+1 Cobalt - 58 1.75E+1 2.5 E+1 Cobalt - 60
'o 2.55E+1 2.5 E+1 Nickel - 63 2.57E+0 2.5 E+1 Tri tium 1.35E+0 2.5 E+1 Zirconium - 95 2.84E+0 2.5 E+1 Niobium - 95 4.78E+0 2.5 E+1 Cesium - 134 5.37E+0 2.5 E+1 Cesium - 137 1.35E+1 2.5 E+1 E
E 4 shipments of dry compressible waste were shipped from North Anna to a licensed waste processor for volume reduction. Therefore the volume as listed for this waste type is not representative of the actual volume buried.
Total volume of dry compressible waste disposed at Barnwell, l
l South Carolina for the reporting period was 4.69E+1 cubic meters.
y r
j r
(
)
.(
i TABLE 3 NORTH Af#TVMEiT STATION i
SEMI ANNUAL RADI0 ACTIVE EFFLUENT RELE15E REPORT SUMATION FTR.ID RADI0 ACTIVE WASTE AND IRRADIATED'TUEE 9!IPMEf!TS i 'FOR 01-Q -8/
THROUGH 06-3f R,','
~
~ ' ' ~ ~
Page 2 of 2 2.
Eilimadofwicrnuclide f
'composiU.on iby type of 690NE EST MATED TOTAL waste) W on.t)
UNIT PEMOD
,_P_ERCENT ERROR (%)
.c _. None E
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Solid Waste Disposition 1
1 NUMBER OF SHIPMENTS, MODE OF tut S:' ORT ATIOi4,,
DESTINATION 1
1 13 Truck B;rnwell, SC 4
Truck Oak Ridge, TN*
B.
IRRADIATED FUEL SHIPMENTS (Disposition)
NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 0
N/A N/A i
4 shipments of dry compressible. waste were shipped from North Anna to a licensed v:aste processor for voheme reduction.
Therefore the volume as listed inr thiS estq. tMy compress 1Nresentativ.e of the actual volume burif.d. lina e is not r.
To'tal voluce a t e waste disposed at Barnwell, South uaro icr the reporting ;eriod was 4.6W1 cubic meters.
Page 5 ATTACHMENT 2 ANNUAL AND QUARTERLY DOSES (1/87 - 6/87) i Ar assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of this report along with an annual total of each effluent pathway will be made pursuant to Technical Specification 6.9.1.9, No attachment required for this semi-annual radioactive effluent release report, per Technical Specification 6.9.1.9.
i
)
1 l
Page 6 i
i i
i l
l ATTACHMENT 3 (1/87 - 6/87)
REVISIONS TO OFFSITE DOSE CALCULATION MANUAL (ODCM)
As required by Technical Specification 6.15, revisions to the ODCM for the time period covered by this report are synopsized below.
Supporting documentation and affected pages of the ODCM are attached.
01-23-87:
Revisions were nade to the 0DCM to update Figure 2.0 to reflect Design Change # 85-31-1 and # 85-31-2 modifications.
i i
l
l REQUEST TO CHANGE PROCEDURE ADM-5.;
NORTH ANNA POWER STATION Attach =ent ?i VIRGINIA POWER Page 1 of 1 11-26-86 b SUPERVISOR RESPONSIBLE FOR FOLLOWING PROCEDURE:
ABNORMAL CURVE BOOK OFERATING WELDING ADMINISTRATIVE EMERGENCY PERIODIC TEST ANNUNCIATOR IN-SERVICE INSPECTION
@ HEALTH PHYSICS CALIBRATION MAINTENANCE SPECIAL TEST CHEMISTRY NON-DESTRUCTIVE TEST START-UP TEST PROCEDURE NO:
2 UNIT NO:
3 REVISION DATE:
a
,Nf'- 0DeM -.3
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.0t'.c E CA t C a c.A Ys n! w weL Swea.a b u a'./
14Y < 3" Asfd heb / rte -a. h.<
.s E -r s*o wf t CHANGES RE UESTED:
(GIVE STEP NUMBER, EXACT SUGGESTED WORDING AND LIST RE/ERENCES. STAPLE 6
COPY OF PROCEDURE WITH SUGGESTED CHANGES MARKED TO THIS FORM.)
Sn //7fich uf /?ta d <J - o s1o ul..e e h we f c A.e n_r
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7 I
REFERENCES:
~,
REASON FOR CE*NGES:
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2.
An- % wl di f - 2.o
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8 DATE:
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CHANGE REQUESTED BY: gg,g g
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0 0
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DOES THIS CHANGE THE OPERATING METHODS AS DESCRIBED IN THE UFSAR7 N^.v.9 DOES THIS CHANGE INVOLVE A CHANGE TO THE TECH. SPECS?
YES NO DOES THIS CHANGE INVOLVE A POSSIBLE UNREVIEVED SAFETY QUESTION?
YES No IF ALL "NO",
NO " SAFETY ANALYSIS" IS REQUIRED.
IF ANY "YES", A " SAFETY ANALYSIS" IS REOUIRD.
(10CF250.59)
APPROVED COPY TO BE PROVIDED TO LICENSING COORD. FOR INCLUSION IN ANNUAL REPORT i
RECOMMENDED ACTION:
DISAPPROVED DOES THIS PROCEDURE CREATE A
@PROV QA DOCUMENT?
O NO 12 DATE:
.3 (COGNIZp'[T SUP SV' OR)g BY:
v.
m An.
/~/9-17 REUXEVED BY QUALITY ASSURANCEp:' '
CHANGES MADE:
YES NO 3
15 DATE BY:
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.WED BY STATI NUCLEAR SAFETY AND OPERATING COMMITTEE: -
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DISAPPROVED APPROVED AS MODIFIED BY CC.E !!EE 18 DATE:
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CHAIRMAN SIGNATURE:
(( [g p
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H.P.-0DCM-2 Page 1 of 6 12-19-85 NORTH ANNA POWER STATION 0ITSITE DOSE CALCULATION MANUAL k
{
SECTION 2 l
i l
LIQUID EITLUENT RADIATION MONITOR SETPOINTS Page Part Subject a
1 Technical Specifications Requirements 2
2 Applicable Monitors-2 3
Setpoints Calculation 2
4 Example 3
J, p t y Sya L fo ja 2. o go A h a n e
9
H.P.-0DCM-2 Page 2 of 6 12-19-85 1.
TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3.3.3.10 requires. that:
"The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the OFFSITE DOSE CALCUALTION MANUAL-(ODCN)".
2.
APPLICABLE MONITORS Radioactive liquid effluent monitors for which 4 lars/ trip setpoints are determined in accordance with this Manual are:
Radiation Monitor Plant Release Point Instrument Number Liquid Radweste Effluent Line LW-111 Service Water System Effluent Line SW-108 Condenser Circulating Water SW-130, SW-230 Monitor locations in the liquid effluent waste stream are shown in Figure 2.0.
3.
SETPOINT CALCULATION i
3.1 Maximum setpoint values shall be calculated using the following i
basic equation:
c=
where:...
c=
the setpoint, in pCi/ml, of the radioactv/ity monitor measuring the radioactivity concentration in the effluent line prior to dilution; C=
the effluent concentration limit for this monitor used in implemen-ting 10CFR20 for the site, in pCi/ml; l
f=
the flow setpoint as measured at the radiation monitor location, i
GPM; F=
the dilution water flow calculated as:
1 F = f + (218,000 GPM x No. of Cire Pumps in Service).
1 l
H.P.-0DCM-2 Page 3 of 6 12-19-85 1
3.2 Each of the condenser circulating water channels (SW-130, SW-230) monitors the effluent (service water, condenser circulating water, and liquid waste) in the circulating-water discharge tunnel beyond the last point of possible radioactive material addition. No dilution is assumed for this pathway. Therefore, the equation in 3.1 above becomes:
c=C i
The setpoint becomes the effluent concentration, limit for these monitors j
used in implementing 10CFR20 for the site.
3.3 In addition, for added conservatism, setpoints are calculated for the j
liquid radwaste line (LW-111) and the service water system effluent line (SW-108).
For liquid radwaste line (LW-111), the equation in 3.1 becomes:
bW c=
f where:
Egy =
the fraction of the effluent concentration limit used in implementing 10CFR20 for the site attributable to liquid radwaste line pathway.
For the service water system effleunt line (SW-108), the equation in 3.1 becomen:
c=
SW f
where:
SV =
The fraction of the effluent concentration limit used in implementing 10CFR20 for the site attributable to the service
... water system line pathway.
The sum Kg+K39 = 1.0.
3.4 The above methodology does not preclude the determination of more conservative setpoints.
H.P.-0DCM-2 Page 4 of 6 12-19-85 4.
EXAMPLE 4.1 The following information is obtained from an isotopic analysis of the effluent from the liquid radwaste line:
Radionuclides Average Undiluted Concentration Released Released (pCi/ml)
Co-60 3.09E-06 Cs-137 4.08E-06 Cs-134 2.65E-06 Co-58 3.19E-06 Fe-59 1.78E-06 4.2 The following information is obtained from an isotopic analysis of the effluent from the srvice water system line:
Radionuclides Average Undiluted Concentration Released Released (pci/ml)
Co-60 8.51E-07
~
Cs-137 1.01E-06 Co-58 7.95E-07 4.3 Calculate, gk radwaske, and service water pathways.
and K the fraction of the effluent concentration limit for the liqua Liquid Waste:
Radionuclides pCi/mi g Released MPC MPC g Co-60 3E-05 1.03E-01 Cs-137 2E-05 2.04E-01 l
Cs-134 9E-06 2.94E-01 Co-58 9E-05 3.54E-02 Fe-59 5E-05 3.56E-02 i
I pCi/ali = 6.71E-01 i MPC g
H.P.-0DCM-2 Page 5 of 6 12-19-85 Service Water:
Radionuclides pCi/mi g Released MPC MPC g Co-60 3E-05 2.84E-02 Cs-137 2E-05 5.05E-02 Co-58 9E-05 8.83E-03 I pCi/mli = 8.77E-02 i MPC g Calculate the fraction of maximum allowable concentration (FMAC) for each pathway using the following equation:
f x I pCi/mi FMAC = F i MPCi g
Tne flow rate for the liquid radwaste pathway is 300 GPM and 2800 GPM for the l
service water pathway.
Three circulating water pumps are available.
FMAC 'for liquid waste:
300 x 6.
-01
./
- [300 + (218,000 x 3)]
FMAC = 3.08E-04 FMAC for service water:
x 8.
-02
[2800 + (
000 x 3)]
FMAC = 3.74E-04 A
3.08E-04 xLW. 3.08E-04 + 3.74E-04
= 0.45 Kgg = 0.55 4.4 The liquid radwaste monitor (LW-111) is calibrated for Cs-137, therefore:
C (pci/al) = I pCi/mi x MPC g
Cs-137 i MPC g C = 6.72E-01 x 2E-05 C = 1.34E-05 1
1
H.P.-0DCM-2 Page 6 of 6 12-19-85 4.5 The liquid radwaste monitor (LW-111) setpoine would be calculated as:
k
, 1.34E-05 x [300 + (218,000 x 3)] x 0.45 300 e=
1.32E-02 pCi/ml.
4.6 The service water monitor (SW-108) is calibrated for Cs-137, therefore:
C (pci/ml) = I pCi/mi x MPC g
Cs-137 i MPC g C = 8.77-02 x 2E-05 = 1.75E-06 4.7 The service water monitor (SW-108) setpoint would be calculated as:
1.75E-06 x [2800 + (218,000 x 3)] x 0.55 2800 c=
2.26E-04 pCi/ml.
4.8 The setpoints may be multiplied by the appropriate monitor conversion factor to determine the setpoints in CPM (counts per minute).
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re'n naast:0 DEIGl% EVIEW #0 LAFETY #RYSIS III1 EAR PGG STATIOi VIRI!NIA ELECTRIC #0 POO DPAY Ot3!GM CNAMGE TITL! / STATION / UNIT; (1
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Containment Instrument Well and Mat Sump 85-31-1 Pump Improvements / North Anna / Unit 1 PRtPARING [hGlhttt/AFFILIA' (3
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-nu F0$RifEREM 1.0 STATEMENT OF PROBLEM The instrument well and containment mat sump pumps currently discharge to the storm drain system.
This discharge is required to be monitored in order to meet state water control requirements.
This discharge is normally alkali due to prolonged contact with concrete.
If this practice continues, it will be necessary to have the mat drains placed on the NPDES permit which will require several preliminary samples, neutralization of pH prior to pumping to the storm drains, and reporting whatever limits the State Water Control Board and the EPA require.
Also, the containment mat sump level must be properly maintained to minimize leakage into the safeguard valve pits.
Since the containment mat sump is located at the bottom of the 58' deep instrument well sump, difficulties are experienced in maintaining the containment mat sump pumps.
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- entainment Instrument Well and Mat Sump 85-31-1 Pumo I=provements/ North Anna / Unit 1
- ntnRING tmotstzR/Arrtur /-
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1.0 STATEMENT OF PROBLEM The instrument well aild containment mat sump /
pumps currently discharge to the storm drain system. This discharge is required to be :nonitored in order to mr$t state water control requirements.
This discharge is norpflly alkali due to prolonged con, tact,.yith concrete. JT this practice continues, it will be necessary'to have the mat drains placed on the NPDES permit which will'requir,e'several preliminary samples, neutralization of pH prior ta pumping to the storm drains, and reporting whatever limits the State Water Control Board and the EPA require.
Also, the containment mat sump level must be properly maintained to minimi::e leakage into the safeguard valve pits.
Since the containment mat sump is located at the bottom of the 58' deep instrument well sump, difficulties are experienced in maintaining the containment mat sump pumps.
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2.o D ese.esptio eC. e.ho mof, Re. vise the. Lit w 3 sechi. s id hie Eukige.riq hview =~d Sa' e.y A % o.1 sis :
5,o Prope d 'Remaiu.hed o7. %bt u,3.i Fire Maz. aves ht y s is, 3
3.4 Al. ARA batysis, 3N E\\ectescalSysw Anty s,3 a c 5 4 dup %b,5 t
Raw iew.4 Revise Ebe.9ettow eq seewas.4 %e Fiuai "Deoiqa *, l.o
=eeuces, 2.o Desiqu Desc.cipto4, 3.o Drew s s/
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Recowh, A o
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, I..o Natsr ats Desiga Ba:its sectio ** 4.4 1
8.t kafr List, o ad i
,f i<cti Delkg =g E. show the addsho4 oO hk chemican f
Revtse the u
stocage ta s, met.eeiaq pmps and Pume codbrol Msb5 ho the **$*i9 Mat surwp pumps, Revise de draw.43 4-Eke co ibe4ed pump citscharge mandeld ia the.w. acte catsposat buildwg o raosa the addikiog eE a n 4 b
od ei. coa avi, Add a sketch in h proemdure be prov ide, a porkabt e w i ew b the. mar sump pump remova.n. Add a. N.e.*4 procedure C P4-Oi) bo Nskail the. chemteat addiboa sfd.eu,
S.o Ac+uan Cha~oes b6 tcP sersons 3,i R.~ise 3.o, 3..p,.ed R esekh'ea,.4. R oveu
,by d w_+i% Pa.memp.
Ikt oad oddig the Follow.q pomi35 's ia Scir plo.ce:
h 1
B.Eus,c.C the p
.-ceh abilihr.S Ehe air cicive.4 pumps ia bhe.
c aia.a memum,em os.~t meu, aue u. e.t.i_,
s, a,,
proposed kht a chemical addibca sy:A.em be cadded bothe.
l contaiducat rent sump pamp. A previo[rted chage to hhts Ceeg.J 0%qe, \\.esced the. p.<9erm etace efe o.a autt scaliaq chenucal
(, Co goa ikcee qua,d \\7.to')."The best was ad rm uistered by Adviseq s
C9exa.kioc a w:t previded poWe vesu.tds bat Phreegd itto' egreat\\3 stowed hke, sca.li 4 $ Tw. wer,ss oC %e. tupact. 4
'9hce.equa.rd 02.to" mm.g %,.>e %e ClaciEsec Deums, ectheDua.ates' product.s. a<d wirk she htc A. Vicq i La Waber 0.o Aret Po 4
addressed with uo weetahve ve.piys. com e hho w e.
co e,.p.~a
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are anached b.this desuga cha.g, as App..d.w.
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a %ci Ma5 Sumig LtprodeMe att / "4 A 95. V 4 iT i U O~I (ts ris,s anaN (carrressis d
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i4 :we thet.: hite c,hemte.ds are'ltet syptiesecs Lea, v.e th4vvyca.l '56wge k.4k. Flow me,hev s are 44 sten. tied nu bhc dtscha,f e liseS ok bhe cook.a.e4 meus ma.h stq pms. Tne e u.h p w t 1 t h e Pt., twe b.sc4 w di epe.re.t.* bbe chemica.t meke. iaq pusups. The Elew cm,hr O the chem,c.o me.t.ec q pumps w iO he fvo p ort to44L b E'.te boa 6 tate o' be.
r co to.me t. Mot su,np pumps. A e bke i w l< a ht4. g,%
hebed leul hire.li wi \\ d=.m
,qise the air t ech..
c, %c-t iw,berige; p,um.ps 5.o.q:5. Tse pump w at be pr ov i ct e d u,.ru bws a@ q uick chscoug cts L.;>
lt w W p,.g 6. be re....ua w.di t
bike bcL.,m a h.ke i4 skr<.uie.ut. w ell.
go i43 3,t Re vise 3.6 Er., AP s A *p' Y.u.i b3 cha.4qiq kha p< a q cw t
- t. rem,p.tyess.e, b RW wea mud h app.o v i de weies 6 bit birsA Far=ig-mf f**viw he Secad 15 pouds b TS p S 8 4 g%.wayqh by mud v ei4.g hhe SoOw=d* **y he he **.cl er be tha.* m.:.g ;
A ppo.v er.6.t.y '12.s ' S Mc.E- \\'r i4% \\ci.t ed ca.w wiO be u.gbcd(ad in e o du'iE and vou.E=Ck "om st, h s(h k igeg.pa.,e ( i% kht Ai.o. G.nch Pep Muse 'tkwgh o, clu.ch h sw., tw, ew,;h k.t e
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W e c.h. ucal sts,q,. area, s.e.wt ku be. t4:,bvv.s.s..*t w ett.
3.3 Kens S.4 AA RA h t af.hi.1r. by.addi.q bha kLt oeq p..,,,,,g bca %.44cirEbe see.ht..A:
% i+i i a m o;.. u.
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(g Mat sump A.<mp T.mpreame u:.s / N APs /uu.s 1 62 L re-te ay,3 us nasasset(aunmop L 4 R e.vi u 5 7 Ete.etricot Systens tue.tusg by cle.iet.w q 6 e.e-i h
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,I clave E ec ho\\ day ba %w.. ~~* gig qqg g e %ll ge,
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v 3s4 Att preth.6.et Yqsa.14 ho.- deOJe w eIIbe (QGak Cd 14 ht ehCnhcat
- bevo.et c **.eC A ue v h ha h hc I 4*i.keum e c h shdf s 3 call o iu.% q co 4Eret eC he peg speed e.ud M wi% out ete,y
-to be i4*..smeu b. w ett a,haCE.
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ingga pas stxng ruummuum O
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l"~i w a l D Est( 4 Adci h.
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,g i t f is - P E 4(., L C..
ds.t play a.4d clevn,(5 s.'r e. 3 u a.d area..
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FIELD ONE (5Nu!GD nonsmars m.: g aggyjg pog gggg muummemwar (1
atste coat m.:
(2 assim omat rnu / starts / arra ('.ut a,we L stru m W e4 w Mat Sn.p fE4.mp Tm ocove meats / 4AM/ ?)* 41 85.51
-l Fc.- la (ss Re.v ise secbou. 2.o D rsig a SeSc.c o t'o L b cleichs mLa ooms (cartamis n e e u.xiq de w seti.4 Aud cad,ue;t it g )
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c a e p u m p w il i
. at 15 couted %rodp \\Dwes in tbc con toi4 meet w
'U4 3teu m e A.it. \\4 en b =S. t bN o. 4g 2." l ineb. "The '2." i s a4e5 act v outed vaderqcouad throgh o 4" PV C pipe bo bh::. weste.
chisposat bu.idiq.The pump wells are1::)v'avided wi6h c.,
t.sthered ut, whic.h wain ope.cate +w o s elegod valves, owe og the disdwge cme ctar Sho*.no4 ciud e4e c4 be cdisduree oO the g
(hetchq pump he Air Supply e OeGif CMfiWC M Eump315 provided Fros the coasbrucit.4 cdc heade< locat.e:6 ouhudeer coubcue we at. A C \\ter, awpres,sure,qQorce oad iubric.ohoc w tI be providedt t a be cheuical sh. age area. at thebp A the g whic.h witi ouew -ceq. d f. peed ad he:td d bepumps. A chen,ica sto
- g. had J cu%esent capac% b.supsly the meter q pumf j
3 %W, is loca.Wd w the che.d s% e rea, b ageros, imam 3 3a The mete.riuq pump w in be coakeoued by a 7. tow mets,
.o the dischavge, i#4e oi the Ma+. Su mf pump. At tte wastadisponet bw14,q the. 2
- tmes kom thc. A ad b swg ctre combi,eh bogethe, e.4h a.
commea 1,4e wi% a leuet c 4hrol vaWe. h va.tec p< wess overft.*mg the cm a.er Aldup ha.uk.L puq3 4 twe weil % 4.
bw provi4e.d wt ihh eguick discean ecb> aad hoses, be aliow easy "feMeVed and =regClaccMc4I A1 AcC CStaq. Ce4*Jhruc tie 4 ach.i9ites Osc ouH#ucd DelM
.Shu r (cest.e. chemical sbow aqc carea':b We'd. be hhe
,a w e m.
- 2. hSkh a ChemiCM $bcwatge b4h CLNd (beherig famp id the cheusca.t %e ama.
A h.bl\\ hhe esid.iq gir sha.bted #4 6e. chemical sb age oreo.,
- 4. h*.k:n%, a \\cd cocky cd 5w4 t be,h id Oc 14st.'eu ment v4 ell.
S. hsta.it hosed wiu qutek. disco 44echs,aud p p,o pumps o.ud p\\ ace t.bem i4 he i45tmment wet 4-6 "
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o 3.8 Re.uw.eeks.4 3.o Aw.ugs / Drawi q Rev i s i. 4 Re
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e ko ** the latex rev i s nog d the,.C.it.wiu$ d r,w', e 3.
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Aed 5%c Lit w,~g cl.aw.ugs Eo bhe Drawi $ / Denwwo Revisio.a Rece,-d t Rev es t - t - F E - 4.(.R i
n essi - i - E - 14oo o
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see.ti.4 4.4, chauqe we hwcee seut:e~ces wear W e e.N. po,.-
4,aph ha etad: he hosesweg app ev.i ma:t=Iy.5 p 45 pe,. f
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p im q com p.4 4t is* k pel ". Apec x i aiat iy 7s ?
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will Be ter.ated i4 enth i4seewm
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5.ch.4 4.9, D.tet.e the esiiring p.,* 9 #*t* aad add h* ball **' "l' Twe pc. marg -.66m witni ttie ope <=ti.4 e4 be r.ysten, witt be 6. ~.J.4 p
ok calcium Sca.%sa q.4 khe, pip,.6g aa.d psamps. k er.hmmiced acial etiead SySt.sm he f%iUim tts. Scaliq has bang de.sig.4.d ho rysham atic ity add eken scais.' A sh.,=3.s ba~ k wi% app,.<i m at.ny e.%ece m=~ tii s 9ps.t G chemical is eu skatted at. each i4strumeat weit. It: wid be de c.esmatq has easpet4.. he. Mat st. amp pumps at lecd. a ce aveq Sm tw.aths. h escka<q pie,.4$ shootd he ch.mic. atty deaa.d CChra. bd.giaate 1rfart: pets c(c1:
whea6 c tS7. checeiro64 l'1 Otta=
a wait aste %, pmp apac i4%e do th W wardose systeu.
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" U inSJ! DER STATICN VUENIA "~RIC #0 PXR CM'#ff 213:2 G/.NGE TITLE / UATION / UNII; (1
OE!ICN CHANGE W..
O Containment Instrument Well and Mat Sump N
Pump Improvements / North Anna / Unit 1 35-31-1
[NG!hEERING REY!Di (CONTINUED);
2.0 IDENTIFICATION CF QUALITY GROUP AND CATEGORY The piping system and pumps shall be designated as Quality Group D, Category 3.
3.0 PROPOSED RESOLUTION OF PROBLEM Based on the poor reliability of electric ~ill(dr ps and controls in the containment instrument well a it is proposed that air operated double di g
used
/
for this service. A temporary ins as n, installed s
at the North Anna Power Static en pumps and has' '[O been operating for approxim The air ' driven pumps ran without cent ous 24-hour a days service for two single failure to dat@.s It l
can be antici t
evel controls, which will reduce
)
the duty of tt t
3 air operated pumps will provide N
long term relia vice.
The level controls selected, operate on the air pressure geneit$ed when the water level rises in a sensin(ly h@/{ '
w de.
The air pressure opens a pilot in the air supp d starts the air operated pump.
This levekcontroller shoul be reli-
/
able in thiqservice since there ar' esso electronic or troving
//3 \\
parts in contact with the water.
As Shown on flow diagiam 7d 731053/B531-1-Fit-34A the containment mat'surp pump will tiAp suction from the containment mat sump which should serve to N
keep the instrument we' 3.1, completely dry unlesss the pump or \\(
level controls fail.
The' pump will be provided with ' quick
~
disconnects and hoses to allow the pump to be easily ' removed for maintenance without having to go down into the instrument well.
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m To solve the liquid waste conformance problem, the new sump pumps will discharge from the containment mat sump to 'the clarifiea holdup tank in the waste disposal building.
Mixing with other water through the clarifier, the drain water from the contair. ment mat sumps would be diluted and neutralized such that th= clarifier fluid will be wit'ain discharge limits.
The temporary system at North Anna is corrently discharging approximately 10 to 15 gallons per minuta on a continuous basis from both the Unit 1 and 2 containment mat sump pumps.
l Based on discussions with Operations, the limiting flow e
through the clarifier is approximately 100 gpm.
The use of i M O
~'
air operated pumps has many advantages.
One of the major ones fg g/
o u
'S.& J a
l y
A ro m t m aatto EGUEERIMi PEVF./ #0 !!T"Tl #RYSIS CJ"' UD I
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$nfAR P3ER STATi0i VIIEINIA EECIRIC #0 POER CDP /M
- ts:a [mact Trn.E / mT::M / JNIT:
(1 0[$13 OHANGE NO.,
. Conta.inment Instrument Well and Mat Sump I
Qump Improvements / North Anna / Unit 1 85-31-1 j cc:mrat m m !EW (CONTINUED}:
(2 t
j is that the flow capacity of the pump can be regulated through the sir pressure used to drive it.
Therefore, the pumps can operate over a wide. range of flow and head conditions.
As shown on pump data sheet DS2, we have specified the following design conditions for the pumps:
Normal Operation Maximum Flow '
10 gpm 30 spm Head 90' 129' The pumps will be initially establish flow rate. On this basis, if two of the rated at once, the maximum flow rate into
'would only be 20 gpm. Since the temporar y flowing at 10 gpm continuously, a ts:o pump be unusual.
The normal operation 'ul.11 pr ne of the two containment mat sump pumps operoting trently at 10 gpm.
The discharges from both units will be headered to' ether to g
the clarifier holdup tank and control valve LCV-LW111, controlled by a level. controller in the clarifier holdup tank, will be provided to avoid the possibility of overflowing the clarifier holdup tank.
This is shown on flow diagram 731053/8531-1-FM-31c.
3.1 FIRE HAZARDS ANALYSIS, Comtastible material which,will be introduced into the well shaft.will be the noses which will allow quick removal and maintenance of the pumps and the oil system for the air supply.
The hoses sre nade of fire resistant material and cannot be considered a t fire hazard, pe_ primary component of tnuineses 2[gn ficap9.
Approximately *f)5 pounds
',, /0 of this material will be in each instrument shaft.
The air lubricator vill have approximately 8 oz. of oil which will last approximately one year.
The oil will collect in the pump itself and be vented in an atomized state out of the vent of the pumps.
The containment mat sumps are not in a designated fire area of the plant.
Approxisctely 100. feet of XLP/NP insulated cable will be in-I i
stalled in condpit in the waste disposal building.
No cable p
I will be put in cable trays.
Approximately 150 feet of 2" Sch,"
, /[
yis N7%}
n, 80 PVC> pipe will be used in the waste disposal building.
q, "i
j is equivalent 150.2 lb of PVC.
7-g j g,
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FORM 97888120 Mi!E215 T.VI$ #0 SITEIY #M.Y313 CJ82130
'" D
'UlEARPMRITATIGi VIENIA EECRIC #0 PMR C2f#tt
^
OtI!M CHAEE TITLE / 5tATION / UNIT:
(1 OE3IM CHANGE ~ %..
((
Containment Instrument Well and Mat Sump k
Pump Improvements / North Anna / Unit 1 85-31-1 ENGIntrums atyta (c NT:Nuto):
- t.
U A review of this design change was completed by Virginia Power's fire protection consultants, Engineering, Planning, and Management, Inc. (EPM) to ensure compliance with the station's design basis for compliance with Appendix "R" to 10CFR50. The review indicates that this modification doe t,
adversely affect the station's design basis for comp 1 with Appendix "R" to 10CFR50.
Additional temporary fire.ha eda dur'ing e o
1 be encountered due to welding; cuttihg, use ink materials, etc. Adequate'precautio
'ary fire hazards will be taken during con tecordance with the appropriate station admin edures.
3.2 SEISMIC ANALYSIS l
This design is not sa ated or seismic.
There is no safety related piping the containment instrument well and N
mat sumps and the discharge piping will be underground and
,si.)
routed to the waste disposal building which is nonseismic as
~
well. On this basis,.it will not be necessary to perform a seismic analysis for this modification.
3.3 ENVIRONMENTAL QUALIFICATION Since the modification is classified as Quality Group D, Category 3, environmental qualification for electrical equipment in accordance with IEEE-323-1974 is not required.
All equipment, however, especially the sump pumps, have been i
l designed in accordance with the high humidity environment of the instrument well.
3.4 ALARA ANALYSIS This modification package does not affect a system which would normally carry radioactive fluids.
The Unit 1 and 2 instru-ment wells are not within a radiation field.
Thus, modifica-tion work performed in these areas would not result in a radiation exposure to the workers. There are two areas where modification work will be performed which are within radiation fields.
These areas are the waste disposal building and the pipe tunnel which connects the decontamination building waste disposal building. Work in these areas will consist of "
pipe installation.
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VITGINIA ESIC #0 SS QP##
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s E3!3M CHANGE TITLE / S7ittM / Wt!T:
(1 Ulmi CHANGE MO..
O
! Containment Inserttunt Well and Mat Su:np Y
I? ump I:aprove aents/ North Anna / Unit 1 85-31-1 ss E3;INtratss arntw (c:NTINutD):
U l
j
' Prior to modification work being parformed, the work areas will be surveyed to obtain radiation measurement so Marg plans can be' formulated for the work to innere that 1
ts
- will be in accordanett with ALAfd. practices per !!,egul di j
8.8, the Virginia Power Corporate ALARA manu r
th Anna Power Station ALARA manual.
Implom n
e appropriate ALARA procWuras will be station health personnel.
An ALA3A Deci en completed and is included as Appendix gas i
The estimated dose o E
onstN etion is 1.275 man-rem. This is bas ours of construction in the waste disposal bu 2 an average ' dose rate of 3 mrem /hr, and 300 man-hours struction in the tunnel which connects the decontamination uilding to the waste cisposal building with an rverage dose r. ate of 2 meem/hr.
- g. g g
3.5 RECENjTRC CONCERNS 3
l Based on our review of recent NRC concerns, Lthere is no applic,,able regulatory concerns for this modification.
3.ti IMPACT OF/0N OTHER DESIT!. CHANG..ES
)
- he containment mat sumps are located outside of the
'A3 contliinment, few modifications are being performed in this '
j aree and to the best of our krtmledges no other design changes vill be impacted.
3.7
_ELEcn.ICAL SYSTEM ANALYSIS Since the cump pumps are air driveu and the-1(vel controls
(,
whic h ill be used also do not require any electrs$c power, there wi'll es ro impact on%e station's electried istribu-tion system fr & the pumps. 'Assinor electrical mod cation s
will be retlutred to control thelhutoff valve at the ilet ',o the-clarifiar holtup tank.
This valve will be a scienoit operated level control valve which wil take its signal from LS-LW118, a level swith which currently shuts off the inlet \\
fb u control valve, FCV-L M00.
g
,saa z,se.4 f.vn p y fd.
{\\ubQ\\
3.s sup nC cas aEvIEw p
3 r
1 This-modi'fication will not chancedlate er ada any i
instrumen on controls on the a w
tuteown sanels or-s
/'])l j j
control room.
afore,ahumanifactorqs s-,
view will not be m.-
g
/
_s-x w
R i
DCP 85-31 l
1 Section 3.7 Insert
~
There are no 480v or lar o
the stations's electrical
.IP has no effect h the station's.
distribution system.
Ther r
GDC-17 lysis, since 1 d
this vol'tage level ar bounded by our ana g
e 9
O e
I I
My
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,s gec
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'c8M: 97eas123 DEI?E.!?G PEVISI #0 S/FT( IMLYSIS (SR!ITfD
"" " 3 ulEARrDERSTATIGI VUEINIA A A7 TIC #0 DER (IPP#tt
^
- tsten cunct imt / sm:en / un T:
n etsran ca nst.no..
O Containment Instrument Well and Mat Sump I
Pump Improvements / North Anna / Unit 1 85-31-1 ENGIntrarnG RU ltW (CONTIMutD):
((
req red. The a r pre regulator vaTh Nt 1 be located close the top of the ins t well shaf owing control o el pump speed and hea out going d'o into the
,,y g ht" @ *0 shaft.
,s N w
a.
- i. - c ;tm ua sgs.
y 3.9 INSERVICE INSPECTION
,. =
This is a non-safety related system therefore the Section XI Program will not be affected by this modification.
3.10 SECURITY REVIEW A security review was per Ld
% n Vital or i
Protected Area bar
'est this modification (Q(e r 11a DesiFn Change Ser.urity 8
~
Rev $ J J
ppendix 8-3.
4.0 RE CHNICAL SPECIFICATIONS g~
^
The containment mat sumps are not discussed in the' North Anna Technical Specifications.
~
5.0 REVIr4 OF UPDATED FINAL SAFETY ANALYSIS REPORT (UFSAR)
Through review of the UFSAR index it was determined that Section 9.3.3 of the UFSAR covers the Vent and Drain system'.
Although the containment mat sumps have a remote possibility
~
of handling radioactive water, this section should be revised to add the containment met sumps since they will be pumping into the waste disposal system.
The Vent and Drain System Component Design Data Table 9.3-3 will need to be revised and a paragraph edded to Section 9.3.3.2, System Description.
Figure 9.3-21 must be revised to show the sumps.
Section 11.2 of the UFSAR covers the Liquid Waste Disposal System at North Anna. The last paragraph on page 11.2-7 should be revised to add the containment mat sump pump to the; list of inputs into the clarifier.
The Liquid Waste Disposal System Figure 11.2-3 should also be revised to show the new lines.
The UFSAR Change Notification Form is attached as Appendix 8-2 to the DCP.
6.0 DESIGN BASIS DOCUMENT REVIEW l
A review was made of the Design Basis Document Summary. The' q*\\
\\
installation of this modification will be made in compliance q-)
1 I
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- s. &
C
I l
i row: nasano FIP3 OWE CUR 900 A-4 nrv.: r m a ggg gy wmm rowen
- '" DoNh*INm'e'nTTn'sNdment Well and Mat Sump Improvement,s/ "
"?
8 -31 1 North Anna Unit 1 FIELD CMNGl (CoWTINUCD);
(18 j
3.0 ACTUAL CHANGES A @
3.
e
- Add the following paragraphs at the gw.0:
L 1e impact of this design change on the icw-level radwaste efiluent stream has been evaluated and determined to be insigni fi ca'nt. "
3.2 Final Design, Section 1.0: Add item 1.20 as follows:
"1.20 Calculation No NE-093, Rev. 0 Assesment of Containment Mat Sump Pump Discharge on Station Low-level Radwaste Effluent Stream."
3.3 Final Design, Section 4.0: Add item 4.11 as follows:
"4.11 The radiolog1 cal impact on the low-level effluent stream and the clarifier system :apacity has been evaluated in reference 1.20.
The resulting impact of this design change on the low-level radwaste system has been detemined to be insig-nificant."
eh([,<
".l /c ds Annotations reflecting this Field Changes have 3.4 # Signature Date been made in the Color Controlled Copy.
t 4.0 SECURITY REVIEW A Security Review has been performed for this Field Change and no compensatory measures are needed as a result of this Field Change.
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W: 97888120 EGifEIMi DEVIEW 40 !!FTf WOSIS (SP.!MND
'infAR PXR STf,TICN VIitilNIA A C~RIC #0 iGER CN#tt
~ '
OE3:3N CHANGZ ffTLt / STATION / UNIT:
(1
- g3g n CHANGE 10..
(2 Containment Instrument Well and Mat Summ Pump Improvements / North Anna / Unit 1
~
85-31-1 ENGIntIRInc antEw (CerrrtnutDh g
with the Jesign Basis Document Summary and will not result in any changes to the Design Basis Document Summary.
j 7.0 UNREVIEWED SAFETY CUESTION EVALUATION The containment mat sump pump modification has been reirie.wed -
to determine if any unreviewed saf questions exist as defined by 10CFR Part 50.59.
ulting determination is that this modification v
resolved safety questions.
1 f
is modification does not in-111ty of occurrence or the consequences dent or a malfunction of equipment important afety previously evaluated in the Final Safety Analysis Report. This modification does not contain equipment important to safety that has been previously analyzed. The it.:tallation work and operation of the containment mat sQmp pump will not affect equipment
\\
important to safety.
2.
The implementation of this modification does not create a possibility for an accident or malfunction of a different type than any evaluated previously in the,
Final Safety Analysis Report.
The piping modification involves small low pressure non-radioactive water lities C
running from a sump located outside to the waste disposal building.
On this basis, no new accident situation is created.
3.
The implementation of this modification does not reduce the margin of safety as defined in the basis of any Technical Specification.
As this modification involves no equipment important to safety and has not increased potential for radioactive release, no technical speci-fication limits will be exceeded during construction or operational phases of the modification.
8.0 SAFETY AND OPERATIONAL IMPLICATIONS This modification will not have any impact on the simulator or periodic testing.
The design change should be reviewed by the Training and
'N
,~
Maintenance Department to update the operator training program
\\~
g [9
_)
and maintenance procedures.
9 f
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icaa: 97at:120 er:1,m tc a s up w g gg nis-
~
fulENI f06 STAT!al VlfGINIA ElECmlC #0 FDG CDPN.Y Df 51GN CKANGE TITLE / STATION / UNIT:
(1 DE31GN CMANGE N0.:--
(2 Containment Instrument Well and Mat Sump Pump 85-32-2 Improvements / North Anna / Unit 2 A
/Sargent & Lundy 1-08-85 RIVI(WING (NGIN((R/Aff!LIAT!0N:
DATE:
(6
/Sargent & Lundy 11-08-85 LEAD ENGINC[R/ AFFILIATION:
A (I
CATE:
(i Da %J /ad-MW "H"
C[5IGN CONTROL (NGIN" [R:
(9 CAT [:
(10
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4W
/l 2/
STATION NUCLIAE 5ATETT AND 0 PIRATING C0m!TT(('APPRC(
(11 CATE:
(12
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I[ <hi' stC INetPINC[NT SAf[if RIVl[W:
(13 CATE:
(14 l
M. C. Cux)iwc"3 12-IL 85 ENGINttRING sivttw ANo sArETY ANAt g *
/
(n 1.0 STATEMENT OF THE PROBLEM The instrument well and containment mat sump pumps currently discharge to the storm drain system.
This discharge is required to be monitored in order to meet state water control requirements. This discharge is normally alkali due to prolonged contact with concrete.
If this practice continues, it will be necessary to have the mat drains placed on the NPDES permit which will require several preliminary samples, j
neutralization of pH prior to pumping to the storm drains, and reporting whatever limits the State Water Control Board and the EPA require.
Also, the containment mat sump level must be l
properly maintained to minimize leakage into the safeguards valve pits.
Since the containment mat sump is located at the bottom of the 58' deep instrument well sump, difficulties are experienced in-p maintaining the containment mat sump pumps.
(
l
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. ?',, Containment ; Ins ent W41fiand.' Ma Anna'/ITnisPW.t; Sump;Pum M A6,ki y85--31 N;"' -
2~
Improvements /Nort.
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ed oh the.::M ME M
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izattorr;of.'. pn.:griort o pumping to;the sto
' drains fand ufp t
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@M'%y'j f}dpro, esfy.'Saidta).n'ed' to' i Af/dQ,'grepo.,ing'idhatevery'AlsoVithe containment dat> sump"1 v thel SCreqiiire7.f! limits 'the?StateJates' Control Boapd 'anD' YEA N.
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^g ;-
t =at ump 'ist. located atl.the botto
~K E 4'.!,~ ',f.E'i 1.5 ';;'deepiinstrs=eotjelr? sump,r.' ikiculties are experi of'th' /D e
d eed;in
@% Q dQS/ A
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- tsme oust nir / mnom / um _
. ~..
h Contain=ent Inst:tment Well and Mac' Su=p Fu=p I= prove =ents/
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Y.O ' M E Y.' -
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, W E @.,ty 2.0 @s., IDENTIFICATION OF CUALITT GRO
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x.
3.:Jj [:. 4.
m,u,
- x.'. -,.*
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m,"e s %y n W M M K $oMibMk
.v t esignated as.h..n.c.., y% g* g, WMM,er. J r.
&* Q;.%
H na piping systent an b
Quality
,c 7.y q:jk' Q 2Nff.' Group D,"catego 1
~ ~ ith Virginia' Power's.
~ ' Np Gik c
u
..., n 4 uclear Powe. r S.
w N
. Assura ME m ' i /.?
T ea
/
Lp h,a
,,.n.r..
l,. A: xy v.. nce Manual (NPSCAM).
,,4 Q 4
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w, s
- y
. a:
w
,, ' %.. a W.c a.s.p...o V//.y " *
.V..l
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.4 G,-
..g 3X' A PROPOSED RESOLUTI
,e v
,7
-w
)
p e,;..,
e... ge m
... w : -,
J...-.-.' b ; 4,;.
m,: ;w
- l d % c., W, m.,e J tea
.,_ ' % ~ y.,....
.. %y
L
.{ ? :
m I
'l '
, GD.,; }
' ' E ' ',NBased on-the,
. a
- r. reliability electrically driven p-s and
,I
'i controls i he containmen*.nstru=ent well and ma*
u...ps, it.
j 2
1
.,[$15 prop ed'that(aibop ated double diaphrag::r mps be used -
4'. [
.,, y (.,0 for;
.a service.'J i emporary installation.as been install 7
g Q,..
. ;O [/ ".Q at.
~
e North. Anna cwer Station using a driven pumps an nas.
i
,', ;;.,h b
- n. operating or, approximately. Six nths. The air
.ven s
,/
N.>
'i.
M, m., g,g'
'?7 pumps ran W '
ut, controls on a e inuous 24-hour day f P ygg-
.. 'v... r. w.9,1
.two monthsvith 'o a single failura o date.".
,9,2 wp 3. L;,ser.vice< f
.s.
It !.<..njw.
< JJ 7
. cart be ticipated that'wi' level controls, ch. will reduce
, g:
~,..
7.
..$ the^
,,y of the pumps',
- e air opersted purgs will provide T-' 'j,.q
P1 ter=,. reliable 1 rvice..",". /c^
' ' 6. ', T :
'f
, ;.. g.m..., y _.y.. g. O V. < N 2 'd..<
.?..p.. '
- ~. '
4.SThe Ievel' controls selected operate on the air ress,ure
..;,.y.', y's.,?.,p 7
=
,. ~.r -
- m..
3' C A W"t I
. generated whe
, f, p air pressur.
the water,de. vel. rises in a' s ing tube. The
~1 M.
'9, y opens a-pilot valve. in the-r supply'and star s e.
g the air erated pu.;rp. This level co roller should be
.11-
"y
, 'able i his ' serv te since there a no electronic or ving Q,q%
part in conta with the water As shown on flew agram 731 54/8532-4*FM-34B the cent n=ent mat sump pu=p will take ' ~
i
's,, tion fra the containmen sat. sump which, shou d serve to
.f y ',
keep the.strument well' cepletely dry unless,,he pu=p er level eontrols f ail.
~ disco.,.ects and hose
.e pu=p will be provi ed with quick to allow the pu=p to we removed for
'Q. -
i.N,
=a i. enance withou*. aving to go down in.,
the instrument
1 l'
'.w 1.
Y' V
.,To solve'the liquid waste conformance problem, the new sump
. w'
-v.
- s,
~
(,
pumps will discharge frect the contain=ent =at su=p to the
- clarifier. holdup tank in the waste disposal building.
f;.',y, Mixing i
with other water through the clarifier,. the drain water fro:
jU the containment =at ' sumps will be diluted and neutralized such
~ 'i M
that tue clarifier fluid will be within discharge limits.
n.
.. ' T.'.
~
x-(
p.
- * *" *[ ' ' O C A
A te=porary system at North Anna is currently discharging ~,
4
%'t /h 3
-r
'approximately 10 to 15 gallons per minute en a centinuous,
" " M 'i ' ' d 4
basis frem both the Unit 1 and 2 containment mat sumps. Based-on discussions with station operating personnel the limiting d)
[
flow threugh the clarifier is approxi=ately 100 gpm. Ihe use
?
9'
&g 4
.>,.9 c.,.,
2 r-u 1,
i as.i.
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,; p m'
_n'.
... m.. v.
4r,
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r u
."M up y
.o
, s,...:
g %, g g j
,f 3:
m,
'? b 7lN DG.' GIT UiB #C *.W:~"y WL.Cl c;P,3 y ag% :
.x..
7 y V.,,. A +
.WENIA flE"Il #C 56 C2W(
ocw me m 1.1;n i
A 9 M9,
.}(
. g*fyg.o MIDI oMal II*l.E / $*17I35 / GAIT-5 Contain=ent hs m =ent a' ell an:1 Mat Su=p Pu=p I= trove =en:s/
J ""
l
,w M, North Anna /tJait' 2
[
1-
' N 'm -
W We,.
d. a!'d j
.c
- e...
tes:s amoa (cwt:m
. '.: t,q,.,d.,., p,s, IM.". ;;;Q:.* cW f,.<'s,. M..,...,D.7 (d)w. n.G.
z.
c Q,
nQ h,$i, 'Cr:
., si, c f
n. O. 8W.,..
N.Q i,0
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,y Wr... - c., h..,+ r
.:.%.yL.,,,. n
<s y
4.'
- ,:'s.tr,n f,
N, M.,"p.,.
.n.; -Q% % f:My.sy. %y yd ; Q,'w:
d.
T' w
.n y <
Myr. :&p i w.?..
+
n v
p?1,#ga :
m 9
~. :s4jf,
. MFJ'p'gA.f. $:of" air' operateti
'w tW,yMs,3,d:
?
W,g t
pu=ps has many advantages.
.'C o
j r
N'
!M advantages is thatCthk flow capacity' b[m,,,,
h
~
I'$hd,. N)'M[QMreg',tlated through'.the. air pres
.i
.M gyQ'gTherefore; the pu=ps can e of flow and 7g M.)
W,s,k n.wp 'b SW we have a PV,f. ;e M %,g./f heati conditions eet 052 b Appendix
~ I. ;=
d th w.ag design. cencitions for the. g it
..@W.'(.W..:h;M=ps; b
~ '
.fM'
.,,.1.. ",,. t.x!:
.., ~^~ S. 6 0 '.1.[. 9 q
..~. n, m.:.u. q a.p. p :,v e,
- g g,
.w w y n:,....
c.n t.qm.; e..w.,a..r2
,~q d$p!:M,[,Ilg,.:d 2 M g ;j.J
.,,' > Normal Cc.eratien Max 1=um w..
mJ aPg
- a... t., n.,s.,.w.:.n
.y p
,.. a.. py u,
r; t.
,+ w., q:-c. v.h.t >~,; M &.v.,.
b.-
m e n.
y
.,, +:. e..
w WW...c.1C spa
. U,.S,,; 30 g;a.
O. 3.l g~2 m ;,
q y
~. W[/(g,hn yf,o m, c;.
mq...
t Of@f
,QRM.f
$ 90L, 3 -y..
O,7129 '
.f..
~V.7M.
U-
. &g.T0fqQs.h,&TfQ":D. T.
.~M+'&9:n Y^.UO Lr*I-
- '.;., ;k' '*,fl. d h ~
S lY$$,$gne pu=ps should be initially set at the 10 gyn f!cw rate. Cn ',)&'
7$.
WN.
-Mik O:;&Qf,this basis, if tuo'of, the pu=ps were operated at once, the
. ? y'W h'!/h NM;}g,g sax 1=us F_cw ratelatDhe,elarifier. would on1y be 20 gpe.
' \\ 6.pkh ;
m s,;~.p..m/h> J iu. sly, a.. -<., pre.g 31nce the te=.perary system ;is only - flcwi::s at TC. g;n centinu, n ',}x&GrJ re.
~
n,,
i e',s, 'n.m-n,Mw two pu=p operation will. be. unusual. The acr=al c
,,., v t. 4 l
., w.
3 W' 3 y :Q,,%p[-!!.e..
,J operatien will probably be one of the two contain=ent =at su=p 4
i'43X i
R~pu=ps. aper a Lng inter =1ttently at. TT 5pa... -
~m.~.;:. -
M. *,L h n
'y:,.x~.::me 3>!,x..y:
3
+
m.;. - g. gs.
..u
. t O p.gw,.w he: discharges fres; both units will be headered together to cjT c...s
.gg
[u '. r t@'b,the. clarifier holdup tank and control valve LC7-L*4111,J.Q:ffcontro i )j@Q E(..,h T
y
.g s
f s
- < < yg will be provided to avoid the possibility of overflowing the
'Q
,q JJ 3 clarifier heldup tank.. ~his is shown n flow diaGra=
- h,3
.v~. 731054/8532-2-FS 31C. ~ n.vi ', - ' ' ' '... -
i
.s.
' s.7
.;,m.y v..
. a. :
4,..
3.',t[ SN,x,,.. ;.: nEAZARD ANALis:5
. ;D,,.
.:.. m.
e
+
+
J' ).gr M
,.m..
~
.p =bustible =aterial whi:n will be introduced into the 3,. s.
... t
.t
. Jt.t
+
Cc
- O" lOinstru=ent well snaf t will be the h0ses, wnien will all:w
'.n
'a f
)-
y;3 '
i _.c;,7f quick re= oval and :::aintenance of the pu=ps, and the oil syste
- - @pI4 W for the air supply.
~he hoses are =ade of fire resistant
' j,2)M
^
saterial and cann:t be.
ensidered a significant fire hazard.
, ;.g The pri=ary q=pe.ent of tne heses is pr/ecer.
ALC(T b n
. g Approx 1=ately L r nds of this =aterial will be i.. eacn ceng f i
4'SI kstru=ent well snaft.
~he air lucricator will have
' ),p
,.,Q,1 approx 1=ately 3 o:. of oil wnich will last approxi=ately one
.,...,.. year, The oil will collect in the pu=p itself and be ventec
.g y
.,s..
J p7/g[g*Q e
. f% in an ate 1:ed state cut of the vent of the pu=ps, 3
g 3N 2Nb
- J.Qaddition, < insignificant quantities of other cce:ustible
,g jj.%Q [
=aterials suen as polyethylene piping are located in the A,f. f, instru=ent well shafts.
ne contain=ent na. st=ps are n:t in
~
f.4 a designated fire area of tne plant.
'#@f
']
e s'd D,
- e.a -
- x. h;a. m j A
s s.
nd,
-e 3-a g,
- q 4
eg,J 4
s
.u.
ns4 9
4.,... '
v
.q l
~... :
O _A d*b-u. i '.'u, L h'm,. - "^
.'-r
- m in AM II.
~
% W & & Q (( & f I
?
.h h 9o 7 f*uS MEEElysixw-
- c.y3,r 7 ',gMp:fb q:yy gp :r/.J:Ty was cp_nty ;
1 A.:g. y fem
+
n.-
- 4. 3%~. Qy;J m:N yy m
%.y
.Qf..i995%f ymm;, n.5: g x.:nc y,;y."m.p %y%%,
'J a
Q.. d y (;.
nwn j
.y
-tsr.a oest ru' / mr.:n r w* ;,. m
(
l.
M,n:ain=ent Instrum enc.,mrID,.m,%f. 4+ac.g.s
, 0..
.r eq.
- 6. ;ig5p oog g'.. <
v and.
a su=
j
?)
Torch Anna /Unir"? N'Mf,*YE.DN/@h,p. Pu=p I:nreve=ents/g).,~M 5{.Ih~f h a.
T d,
b_ "'f d'A'k n
..4 3. os:3 d, ;ys. cmm mira. (t:wrmann, :,y ~ r '
s.>.
.4
- c. k 4.y. w. m W..., Q.') %y,, M "
4 w
c.
~
p,,, rw gJ
~..s-
.in W j.*%,U.,C Q *
<. 7. & ;%1'
$Q) g*hy:,,,y.%.t g,m
% pag %y 3 f.
6?R
,k g #u
&?
]O5&
g y
,A
[h
[
proximately thef.4aste/ dis % feet)d 2MthdEV N.
,in.
- h, t If
' W.
posaf;buili:ff ag@l. Th J
Jbs of.
MDM g, %
EVChappFdxhately$0Gffeet' pe will be N d,.
%7W k Med.In: the'deEdntacri ~ ic
.s ' equivalent to /C M1h? N. iq
[T. A,gothe%cu:bustible,90Gllbsyf}g7C"$ '
. cant quantities of. f'l:[p o
' '.M.y :,;':c;, Q [g. k% htlocated'iiCthe#was C
'Eb
. as polyethylene pipingd "e f f:/.j af buildin6-. OOlR. Md'.,Tdz' Nb
, r Q 'f f M, N $ M D k @ h k M F M. N & ['i h M; M M *.H
. Wthis design change was cc=pleted by Virginia Powerg.
('i M
5#
kAjevieso
~W 3 J bCQ2 ter ensure ecc:plia;nce with the station's design basis for W,%
. i,MMMecmpliane[with"Appendir'"R"",.to 1CCFR50.'f The review
'"W%
NM
- . L.pqg;Wf that this.medificatica.dces not adversely affect.ther station',s; ?
. f.i, -
'M!
. QW.f.;/Midasign1 basis 1forlccmpliance with Appendix,,"R" to-1CCTR50..a "h;%
i
'kll
~ ;^' h] : ?
.hhh&$.$h&
Cf g j; g Additional,; tempora & & h h W M ' & $ U h hj $ Y sf? h 5
ry!, fire hazards during ecustructicrr kill-be w -.jjy
' S.OWyM(encount' red 7dueE'tiweldish. cuttiiig,'use 'crhea
' ~ y4 ~
i e
X f?q.QlJyhazards, wtlkhe,taken during; constructierr in accordan cateriaIs,$,*,etc@dequate precautions for;the tecporary fire
- l.g.,the appropriate station administr'ative procedures.
, j y yQ
~
' %2'?hWN$55&U$lhY.k'!-k. S.? gp'%' ' ??# W Q. W', -Q'.
a 4.
h b&&'i.8
,shS5% & "
' s
.M SE'SMIC ANALYSIT kN J,
". D 4. T; r..
yp}.hl1f This:desig:r is{ cotisafety related cr-seismically qualif M j' @ l QYi % h Y.
h
' d.'.,$j
- e. ;,
'ff ; f D. ore l's"rdafety[related" piping in the contaic=ent instru-f
.,..,. ', #'h. ent 'welf.'and',j:atju.~ps'and the discharge piping will 5e
, 4,,f reuted tas the;(wastej disposal tuilding wnien is acnseismically-fMlg I, c gy. g-
, ~-
.l" U N'. qualified.OCK.this basis; -it will not be necessary to perform E.
SV ~
a' seismic ' anal /sif for this modification.
'R:p'.y g(M ygp:Lhy r y -
f,
.f>,
4
^
~,"1 f
' ?"qfg 3.3 EWIRCNMENTAL CUAL!?ITATICM W.
M~ Ma ?
x 9,M g -
. y e k.,g. %,s &. & w..
m g,yt 49 CySince the modification is classified as Cuality Group D,
,f w
, S. Category 3.,'. environmental qualification for electrical
- %W[
~
=-=Qg sequipcentei'a acccedance with IIII-32 3-197", is cet required.
g,g Equip =eq included..in this = codification is not required te te 3 'a '7
> 2J.i added to thel Enviren= ental Qualification Master List ( EOML).
4 #*
I Mg '-
1
.3 MD.e =acerialsf acd equi;=ent.usec or affected by this ::ccifica.
m ticit d(nctifall in the category of 1CCFR50.:49(b)(2).. AlL s'
i
.. equipeent,' however,' espect' ally One su=p pumps, have been
" n..;T...w.o
~ 4
' designed in, acccedance.with the high humidity environment of..rk " L s
..s s.
. the instru=ent well
'y.2, M M Q C&,lf) f' Q &;,.l h f'.,.. n:.,..w.,.. & :,
v
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'ALARA ANALYSIS w M
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[d y;
contain. f. t ontwo., area.s,
,.. Uni $kW' p
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=e j~N' RW.L.&,&.Iccationsnt' mat. :*(and:.i,nst q
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- a...' N li@M %h11sbed viaEtelesihone 'c.reas ar. e a
. p conversation"with Mr. K id.utippard' of p;. ;..
~ <
l$.
Q W g M* phi N Jd,mp@fViigfdiEPcVer2 Nove=ber M985'. D2$r$$.@dhWwme@.M y.,-
teffM m m ekemc h Awi
,,.7,'..
. J,,, 2 i i4Lg!The c=ntain=ent mat and,instpu=ent. well'su=ps' ds : net norially'. T jy',,
Gw han.dl.e.p_ad K ; the su=ps".ioact,ive ' fluid, s.,.ItJis:un.li.k..ely but possible,'. tha, t '
j.'. M*9, m f,..
.6
. =a y".contain radioactive conta=inants..Ihus,; price.. '
'de
., " $+. +. g d.to s ~e =.edif. i. cati. c.n Wo.rk,,b,ei.ng ' perfo r=e.d,r. the station. heal.th,.7,1/.%
~
th
.J
. Q I
-,', (' q, ; ;;hysics depart =ent; shculd sa=ple thel sump fluid and obtain g
\\
' J..Qs= ears fre,cs, equipment' located, within: the su=ps (e.g.,l su=p j
y,q
{
.',* 7 ( %;pu=psh: to deter = ins whether, radioactiveeunta=ination is
- (
.,. cj k.g
.fipf.ppresent@Addi$1cnally,f the health physics depart =ent should s
-obtain radiation surveys of,the w 4,%QM;q A>
. areas.jThis includes the area. a;. ork areas within' radiation
[,
l4 g round the A su=p and the pipe
. W.M 7ecuting paths Lwithin the' deconta=ination building,' pipe M:nnel'
,, 'and wast'e dispos' l" building.70epending an;the results of the [Ng '
', i a
~
? '.QR ;
radiation surveys sa=ples and; s= ears, the ' station. health
- *g, (-
g N
pnysics department wcult deter =ine wnnt action to take to N M %{g
(
j assure ec=pli'ance,.with Regulatory Guides 3.8 and 3.70 the
< Virginia Power Corpcrate ALARA' Manual' and the' North Anna Power '.
.gjg? ;
~ " W.
l,iStation ALARA Manual.
~~
- ,'W $lN&QQS }$ { (c ', ;.'0.j,, i b N W ' ' A'l,,
'I $
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.75 d 8 ' h. %.L c'
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?.The-esti=ated dese. obtained during = codification work within.
'k; fw t
.. radiation areas is:.4.0 =an-re=s (2.E =an-re=s due-te work en-.,, ce M $
F
.U.. the ; A lsu=.MIhe estimated 'dese valuecis' based
'I 1
M syste=).',
v i
/l.Q,,.SN@
=an-hours)1 thin 1 radiation areas and 'aversge dose rates. Two
, thirds ef the construction.=an-hours, are assumed, exposure 9 g;p f.vf ~
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'" related.. The construction' =an-hour values were deter =ined by..' ]'pf 'y
. W
.aVirginia. Power'sJ & 'C Estimating Division-and are broken down.v.:je t
m as follcws: work Jithin waste dis;csal building (790 =an-1' j f
hcurs); werk within pipe tunnel (c00 =an-hours); work in botn A and B su=p pits (375 =an-hours). It was assumed that work e.
i m[ f%
('
in the su=p pits is evenly distributed between tne A and 3 s m.g.
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.initie I;*,
M' d m h h., $ M.isump~:was? consider
' g.fty h?h?gtYfjgBj[the 'A:'sudp ;iipin[M'e nJexposuref.7CnlyM~Y M
'a 27 pie 8'. tunnersan%bs tof the, A sump system.1The d[?
. pipe J.innel' so 'th e"Y*'
l tt
$, g'I Y[$ [d.$
'.*gy,,.p san-hour,se.withirr ther.fapwaste disposal, building
,fjp
.y 7 i.'
y r@g%;j'lgf.," Qand 3 sumps. z.:,Cf,the,79G. san hoursr,4' 22 were applied i
J'e:( h:.;5.W, :% man-houp values (.IQwere; applied to the A.
sump.syst er and Tlitse.
-4 0
' I:..idMhd Average dose rate jaluits,Vsed;,in determining
'M
. N dgiKIjkithin the wasteltisp'osal.buildirig for each su=p.. system.
.i.j F(,A*
i.
y, M Q; apexposure associ'ated'with the-A sump modification were: ' sum w
r Q ' '*
$4Cf6 area (2.G' mrem /hr)f; iip' [tunnelj3.Umrem/hr), ~and w'aste
',h
" ' l-e
.J'.:.J.plDC^.redisposal buildins (2J.' ares /hr).i Top the 3' sump modificatictr,.D ' ;
' V, Mkd }Jdkradiation' exposure i'97
,'.yeMOT/%gNSdisposal b'uildingM,for,5cdific' tion work is'onl 1 the 'aaste $k a
, W, ;, l y',b2 The~a% rage-dose rate.value used was 4,86 h i Average, dose Yate balu'es' were ',de't
% mrem /hr.Y
'Wh Y.,
41, h. 9 6.m wMi,}.h radiation survey maps?$fths '
g g gsi? % y,q'by g y yl;,g g Q % 4:^.
~
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.:.,,y:q y.4.:@c.m@y Vtrginiz Fouer;;&. areas
..W v
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- @i,:g@ 6he Engineering ( ALARE. Design (Ght'de'* required byf
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.this de sign ch. ange packa ge.
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- 1; Based en ouf review of trecent' NRC ' concerns, there is no N
, s, ?.,,,
(y. applicable. regulatory' concerns 'for', this = codification.,*
U
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.v. ' f y;(outside of;the contain=enti:rew modifications are being.
. M,5 ; g@}
4, performed in this ' area' and.information received fren Virginia ^ ~ id i( Power toldate" indicates that no other design changes will te L
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. ' >~ ~ t<
' pumps. Al
, the level contr*
Wnich will b d do no'O
iT a-;f "'
e
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- e will,be' inor.
(
7,. d G. Q W.$ red'. ion on the st
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A a. M/
a result of triis modificatient
'N 6 '
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(
4 there ill be no 1,7 pact on the GDC47 ana ysis by
~
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', g ;
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, Program will not be affected by this modification.-
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e ' A securttY restew. uas performed and L.t was'T.ound that the
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- design change does not: ' create an opening in a vital or
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4.0 REVIEW CF TECHNICAL SPECIFICATIONS
';y Through review of the North Anna' Technical Specifications, the contain=ent instrument well and mat sumps are not discussed
' Q, and therefore, no changes are required.
,..,5, m e 4^
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g 5.0 REVIEW CF UPDATED FINAL SAFITY ANALYSIS REPORT (UFSAR)
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Through review of the UFSAR inder it was determined that t' Qih
, e'Section 9 3.3 of the UFSAR covers the-Vent and Drain syster c.. E['
wc
'and Section 11.7 covers the Liquid Waste Disposal System. The Unit 'i DCP' 35-31-i revised the UFSAR Cata Table 9.3-3, added a a
paragraph to Section 9 3 3.2, revised a paragraph on ? age
.[. :.% %
,1
.71.2-7 and revised Figures 9.3-21 and I t.2-3 to show the '
. ji-pk system : modification. For Unit 2, the' UFSAR Figures 7.3-25 and CA
- 11.2-3 =ust be revised to show the contain
- ::ent ' mat m.xw.
sump pumps
, 4,.,and the Unit '2 discharge lines to the clarifier hold up tank, ' ';,gggggy 0M. Cj' jp
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..R respectively. '. The UFSAR Change Notification Form is attached 3
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' as Appendix 3-2 to the CCP.
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NS A Aminstallation 'of' this modi.
'be-made-in. compliance j
"9? NN g*ldM.'.;7witi:the Design Sas ary 'and will ncc result in
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9?? crease the probability of occurrence or the consequene es,
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erent type than any evaluated previously in the.
hW Final Safety Analysis Report. The piping modification a
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'fication limits will bei exceeded during construction or
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dtSckurq e ka.ig meut ma.h sq p,wes.%e
.w rw e.b.sc 4 w di epe.ca.k hbc chemica.l c whPwt a meber:49 p.ou at. The tte.a e a.h. ok we chem.ca\\ me.tec%
pw sps witt te ev-ortio u at b o t'.se k e.at.e.',. b e.
c.c to. 4 tdesh, tuor op pmps, At bke 1. u lu ) hH,q,hhc he.h. d leo t sia.hdi uit de -wyi,e the et,<M i o cw twe.ter i a.e pum.ps S.o.q:<;. %e pwrips w di be p ovided with hoses g
ad eg mew chstou= cts b a.ba tke pi n 6 be ren sed w.wi.wt go og tube bet.tc s 4 (.he i4 skmneut, w ell..
3.1 Re.< sse 31 5.s. A u d s A-+ ' y.ua b3 chaq q Wa. p<,,,q conivt 6, p.\\gester t WAi. 4. A Eh. 9p..v s mus w.ip 6
~
2.s go
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%waggh
,a M en&g.heSeL\\ew=d 's 9 he khe Ed er kha (%rga,vyg g g k
A.pp<4' ier.a.y 22s* J 4e.s- \\'T i4sw\\a.t.d c w. w a\\ de m m, \\i gh k a ake gs,s.,.,e ( i% kh e tuskade.d tal e ed'ih cid v"ou ked g
l Aus Mr d Pump Vev54. Wmg o. Ack % h,, Wmh bac el 43Sem.: Mdia6g, % yh.i. sasc.a64 9sch. hs.*k,J Lo be ch. mica.t st.g. a.cea. N.W.%D b khe. 143hvu.sisseh w all'.
E 3.3 I tvts.c, $.4= M RA N 8'\\N h CLddi4fg
.h*
- 8^k9 pqQ he the h4 c$r be sechte4:
A a oakd i4 I dos e4 A8 ma a n a s w su b e a.bmi a ed au.v e q bha. oddihee) c eusbru.chied "I'hss ch be. sed.a So s s hoos w t:he wa.ske clispo.at bustdq w&aa *%e dos, va.he cr 7 Mieml M a A & w$a hou,s in bhc I4shvuaisak. W 6L 2 A.
area at aa J.-/h 4\\ENg
- ,.;)
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- -.... - ~.. -
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- *' 8 IIn f)R m e s u n a j
nummmanswer
)
usam ommu ims / smin / mm %m,nea ras
,m,,,,a w.a (i
este amar m.:
(r w %.t symp Pump Improvemeur-s / NAPS /uu.s. 2.
rc*lo F 58 mesE (CenES)*
(is 54 R e.v ise 3.1 Eteckrseat jysten i A waivai s b y cle' et. 9 5 '. eman,q,e o
g p,<m $r pw a ad i a sewei $ +.ine c-tw ~ m:
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s.o.4c. A re ~ itbe 4 i m pact ciu we ts af.. %
s 2,5 kwo etee.V.wca alt shv s Lei.a sq shent, A. w w< e et *~c.6 e.a\\
m edikiC.A.ito W il\\ be rega'irec\\ (
c.% ho( the aaAaA M y4v4 at bhe e 4lah L.n t-he,cla ell.iec hotd' p be.gw.. Tgig ggg ye y){ be (
a s.\\ wotd ofe<a.k.ad \\ =v e L coubret v=We wht c h a d W we, W siguat t.% t.t -i v4 u e, a \\ ew et g be.w.wk Ah ebv ceaug
~
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me. are. ~ 4eos. W Edd 4% 'ws d.w%
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- ts
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co ut.rets e,~ kh e a u = ita q nu.t d ow a pa a e t s. c. k r.)
Voons 'have.et., A hu. mag ha c. hows fC 0 4 M wt 11 Moh be Yequired The atr pnssu.ca, yaqu.ta,.6 On.tk willbe loca(ed ia be cNsmscat 5%c an.ren nev.b b. kke. t4%rumech skiC+s 3 all.w,%q co ubret oC he pep speeck cr.ud had wi%
ut age,q od.
6:h e i % e 4 h:. w e.ti s w J t..
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i
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W.8 I M1DR P005W1e seusm eewer (1
m ia m u u n.:
(r m is onn u i m s i s w im / s m g.,,,,..,.,,,, u,,,,,. w,,
P Ss n-2 r.: = (o m m %we.-
s / at Os i Um 2
,.., :.. s..s FIED Guss (cafftaEB):
(18 EiM Al D ESIG4 g tb i s.:
seckion t.o Fe?.<eces 63 acid. *q t:h e F.tlow a * $
Acid b step 1.tB se De w
itoso -
E ciekcu ts ca.<ea..
P aa exad J. 6 i l
D"c k l*
- i
~
. 4'T sheat.*e m a e
e N.
.%..y.
u
/C
'O E
4
...._. m
..a_.._...
4
== mas nasone emsem l
- '8 m um mesana menssemer
'"" *** * / "t* / ""' c..t....ut re stru ue.at w.ti n
mis oma m.:
<r aad Met b, Lp h er.
muts, / 4APSI det 2 85.52 -2 Fc.- lo l
nas oma temmen n,
3,1 Rev ise sechi.u. e.o D.s,.q u 3esev i ptno4.by clelebyg khe eAtttv43 clescespht=4 and oc%d sug he. blice49 b
Air opeca.te:b de%.bte dia phrn.p p,ggs will be used b-the co4 base me.at Mot suup pump suvice. I4 each eu,up, ege pump u ill be provided, h discharge o9 khe coataia meat mat is routed %:uqw 6 b4es in hbc
.T.asteu me ut W eti km es. t n q 2." iines veuted uadergrovad throw.q h a u' Pv c p,. The
'2." liaes an.
ipe 6 Ek waste, disposat 6 \\d.uq.The pump wells are previded wibho t<.thered ht. which wit \\ ope.cate +wa s eleged valves, pac.ea h d.scharge 4the air h*.ioa oud e4e ca bie. disc %niyo? hhe meket.uq pump. The die suppiy be hea' dA belmps is provided % bhc coasbructi.
locaed ouEsided coabain we.st. A. C.\\ter, airp us 'lubri cak.c will be provided e%l ab thetop, A hhe su9 e
w ill att W eSh a*
had afi.bhe. pumps. A chweg stor.ge haak seat capaci+y 6 sup% the mete.c,q pume 6 appros imat q 3 mus is1.cewa ia the cheal 36qe area, L mehreaq pump ett be c abro\\ted by a C.t.w m.w io tw discharge, te4e ot hhe Ma+. Sump pump. At %e wamiteolispeant bu,WH 9
3 l
Ehe @' teg. rem the. A at.d Psu9 are combweh 6 ewer w ho a.
commw lepe wi% almues c.4hrol vaWe. % v.tu pr.vews werF)%,4g the Cto iCi.* tt.ldup haak. L pug,,a b e weil W b<w prev ided w ihh agwic)C dise.waa, ech.% odd kloses, be atiew e.asy rem vat ad c.placeseat as acce.Saaq. C.ushn.a:ti.4 dchivites are eu.Yl:4cd Deled t
W\\ic a
b ed be khg i45brument v4eO
- 2. Lsbun a chemical 5%e tu4k od freberiuq pump id the chemicat $bevage aven._
- 3. hsba.6 Se es.ie.iq air ska.hted 84 he. chemical thereqe ocea,.
.4. I.4ShCU, A \\ed co4kvol sw 4 bch id Oe 14Shru meat well.
- 5. hstatt hoses with quick dise.og.tecks,aud p peg (,(.he pumps aud p\\ ace them i4 hke i4sbume4h weu.
i mdM
^
- g. c. 5
m..
mm: nesses FIED OWEE GLPRBetD
"'8 Milf.Nt POGt STAT 101 wwesamia nowse ot31m owat fritt / stutos / tart: bo kaiu w h st ut Wen (1
oesta cimat m.:
gg 85-32-2
(~4-to and Mat. SuW be ~LMeco<eue.uts /sps / Vuit 2 5.8 bise. se ch. a 3.o 'Deaw iues / Aw ug b isi.u R ec. ds "*
Fitts omsat (corrtme):
the. L atest m tsteds of the @ot\\ouiq d raw v.tqs be sho J Om/
73t ose / ess2 rM - me -
3 731 c 54. / OS 32 FM -34 6-1
't31o 54 / 6532 FM-81C.
3 73 o 5+ / 8532 F M-90 6-
]
NIO TSL o 5+ I 8532 F S - (O.
g, 751 oS4 / 8532 FP - 29 A-3 l 73 os+/ ess: FB-Sqc.
l 751054./ 8552-S - FE -32V -
I/
Add the. Es tlow la43. dcaw ings ho f.he Drawiua / Dra.w,q_,
Reusieu Record :
. A h.,
Suhl."
t
"~
i dS55% t-11:E. - 46,R ; 7 f J ',; 'y i g., q,. A I
MN"f
'*i-rd bS S2 E. -11o t(
IW ; g
.W 4 85 5 2 E - 2 2 co.
y M/s2 a es 3z s - t4eo.
o I
8 8st2 1LP 1 AFl-3.9 b m sec.k.t.~ 4.o hq sh as 9ett ows :
Sec.b.= 4.4 L. We Giest., pamqmph,ahee out oC.be veuk oC. khe i
dete+e therest e9 % paqraph and ada % bttow i~q.
puses i Wehoses weagh approv.i m a.v.ny 1.5 p -eea p.c 6ce oud he.
pesenarucal). k tiborsqe bAuk of suCCic.aemt sit.e to Systenabscathg bo hetd app <ou e. etely o thee.. mouth supp,g.9.ch.%ea k iushu.4 av ene.h i4thrument weu. It w A be ae.e.e35.q 6 i Asped, the rmA tuup Pumps.. ace e q thru, me=hks.%disch 3e. pie.$
show Ld ba chemcatty cleaned w heu ai. LS% decrease i4 Volume occurs bidegu. eke spare parts ace. availahte 6 pumprepnic ia the M APS w arehoase sy stam,
. ~..
- d 4g'
,s,-
Q W
/
t A N h e7eI.
.-..:.....~.~.....
-. ~...... -..
a..
paun nosens FELD ONE GNt9BD m.: 8 M1DR 700 STJ(n(R vaissuessomer anim oesnt T:1u / mite / arti e,q.
,,,,,,yt
- ,,,se,wy.ys w st (1
ante oewet s.:
(t A 4ci M at Tany b n.g S prowc M en u / N APS / h.6st. Z M Q-2 R -l O rtas assus (contrans):
(ts 3.to Re.v ise seaEios S.o Inbe % sceih by c,le\\ek q bhe, c is.biq sp.t..m.kese,:i pl
~d add. $ hke C..it
. g Twe.g.,,4...a J we.e w..4m.~s e.t some g mp, witi b LLy a.Jema.hc. vjheu b. L e v ci en the i +45% eu m e ** u.en *-a ses the.
Icet se t.ek t the.
- Ca' s.4i.q, it m itt e 4ergisc. two sovy..a e. 4 b d.u.k.,g..C = chem c n meEeriq eu, g, and 4,.4 %. 4icA.; e asec y tokig sw.ti.
. N mie N we a eqw.i b3s ou se h c.ubai-ameat m.t SW Wmp be c 4baium.A *d suaiy ca,.9 t*
% rutsens.ac. ou s q pump w.it
..; W c-k. im m, -t.
infect a. a.46.-
mat ma y eum., ab hs th= k ~e p*,..e.tiseka m h w,
Wh W l ve.1, se ekume t. w it.imn 6. % *.wi W, q,
s it t dll cdesw 3,se b 5.o.v. s, sh.ypiq bhe ue.t sus.p ynneit ad chemical rm.E*ri.g pum9 L. sp a..A. tis %. p,.
,..f. % - w..
..t..wi. % n.f p,.p c be.,gu.saW by the use athe air pec.wure q t.w anddisc.A45s,sve. b Nwv4 % m vep\\.kor i
i New. It%:4hewa M r f % uir.rved k% i ).Lt v ergu.afe %h h go.mgas SH to be putt.d.ts.a-k.,q. c4,,4s ee.w.J L. w.,% comywe*As as sc i,3 f'. req a%d obev camp,.ab5 i.6 % m.4 hi p pq suchi.a =*4 disetyc,,
j N
p.w skoi ta cus. be i4 specked.Whe.4 t:ht.
- a. oC. W cAis.
dey,. piriq W desecased by IO.t:he 4t%st p 9,3 sd bc chermamuy clee.4 4. C....ki. 6s 4., eb..uy aae b..
r,wided. A t.:-
h saalig ch.m ie.A \\.ven sh.und be, mowi&
d
..$ bb chem,e t %e ka k."tT s c f h.I- %. hen.c.A shevssgs bm k witt p,ov 4.ignyvmie.%
TO %
- rq *4 aati s.48.q cha..cas. Ch*w* k uWs witt cL p d up vwak siaait Pa=f "f*'*h'M hw=, *1 s w h
- h
'S "h"* b l*P--*d 'a. '
Act puh. sp..e p.a, are awaiww be puq reg;c.a the. M..w A 4-4 warshoma.,==pt.kse.
s9 L1
[o,
Q f****
gh 8
hh5 w: nasano F10.D OWE CU9 LAO'D uv.: t N.C. EAR FOG STAT 13 vuncursa PowEn (t
Ot31GN CHANat No.
(2 CC519 CHAAGr TITLE / STATich / uh!T:
Containment Instrment Well and Mat Sump Improvements /;
85-32 North Anna Unit 2 (16 ritto enanst,(centw.c):
3.0 ACTUAL CHANGES to DCP 3.1 ER & SA, Section 8.0_:
Add the follwing paragraphs at the end of section 8.0:
"The impact of this design change on the low-levpl radweste effluent stream has been evaluated and 1%d to be
~
insignificant."
{
Final Design d N 1
llows:
3.2 "1
ul o
, Rev. O Assesment of Containment Mat Sump Pump Discharge on Station Low-level Radwaste Effluent Stream."
3.3 Fina_1 Design, Section 4.0: Add item 4.11 as follows:
"4.11 The radiological impact on the low-level effluent stream and the clarifier system capacity has been evaluated in reference 1.20.
The resulting impact of this design change on the low-level radwaste system has been detennined to be insig-nificant."
3.4 [ Signa ~tuteME.,< q.ng Annotations reflecting this Field Change ha been made in the Color Controlled Copy.
Date J
a.0 SECURITY REVIEW A Security Review has been perfonned for this Field Change and no compensatory measures are needed as a result of this Field Change.
i a
t et 8
p:.
/0 l
Page 7 1
i ATTACHMENT 4 (1/87 - 6/87)
REVISIONS TO PROCESS CONTROL PROGRAM (PCP)
As required by Technical Specification 6.14, revisions to to the PCP for the time period covered by this report are synopsized below.
Supporting documentation and affected pages of the PCP are attached.
No revisions to the PCP were required for the time period covered by this report.
1 l
I l
Page 8 e
{
i ATTACHMENT 5 (1/87 - 6/87)
MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS i
i As requirtd by Technical Specification 6.16, major changes to radioactive liquid, gaseous and solid waste treatment systems for the time period covered by this l
report are reported below.
Supporting information as j
to the reason,(s) for the change (s) and a summary of the 10 CFR Part 50.59 evaluation are included.
j l
i No major changes to the radioactive liquid, gaseous, and solid waste treatment systems were made for the
\\
s time period covered by this report, i
i e
l
\\,
4 u
t
(
________L___._____
_m_
____s
.s
'k Page 9 ATTACHMENT 6 (1/87 - 6/87)
RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION INOPERABLE As required by Technical Specification 3.3.3.10.b and 3.3.3.11.b, a liy: and explanation for the inoperability of radioactive liquid'and/or gaseous effluent monitors is provided in this report.
On April 11, 1987, 1-RM-SW-108 (radiation monitor for service water discharged to Lake Anna) was declared inoperable. The service water line to 1-SW-P-10 (service water pump) was found clogged, which prevented flow through the radiation monitor. Attempts to maintain the service water line free from debris and return the monitor to service have been unsuccessful. The 1-RM-SW-108 (pervice water radiation monitor) was inoperable greater than thirty (30) days, because of difficulty in cleaning the service water supply line.
f L
t t
i
\\
________-_____._____________J
i Page 10 I
ATTACHMENT 7 (1/87 - 6/87)
UNPLANNED RELEASES i
As required by Technical Specification 6.9.1.9, I
I a list of unplanned releases, defined according to the criteria presented in 10 CFR part 50.73, from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents made during the reporting period is made below.
)
No unplanned releases, as defined according to l
I the criteria presented in 10 CFR Part 50.73, occurred during the time period covered by this report.
/
i
(
1 s
t.
'f; e.
Page 11
- l (01/87 - 06/87) 3.
l Changes Required By The Land,Ude Cpnnup Evaluaticri l
e I
\\
As required by Technical Specification _3.12.2 l
and 6.9.1.9, Evaluation of the Land Use Census is to'be made for identifing the new location (s) for dose crlculariens and/or environmental 1
l
~
monitoring pursuant to Technical Spe$fiff;ation
,3.12,2 requirements.
4 4
l No Attachment required for this semi-annual radioactive effluent release report.
?
t t
l
./
t t
s
'g, 8
i i
i 2
.' i
)
,.+
v
I Page 12 ATTACHMENT 9 j
Lower Limits of Detection For Effluent Sample Analysis j
Gaseous Effluents Required L.L.D.
Typical L.L.D.
)
Radioisotope (uC1/ml)
(UCi/ml)
Krypton - 87 1.0E-4 8.56E-7 1.21E-6 88 1.0E-4 1.02E-6 1.29E-6 Krypton Xenon - 133 1.0E-4 7.38E-7 8.36E-7 4.57E-6 133m 1.0E-4 3.63E-6 Xenon 135 1.0E-4 3.61E 4.99E-7 Xenon 8.97E-7
)
135m 1.0E-4 5.84E-7 Xenon 138 1.0E-4 1.43E-6 2.12E-6 Xenon Iodine 131 1.0E-12 8.43E 1.00E-13 Manganese - 54 1.0E-11 5.80E 7.40E-14 Cobalt - 58 1.0E-11 6.21E 9.16E-14 59 1.0E-11 7.33E 8.83E-14 Iron i
Cobalt - 60 1.0E-11 1.19E 1.78E-13 Zine - 65 1.0E-11 1.44E 2.83E-13 l
89 1.0E-ll 3.00E 1.00E-14 Strontium
)
90 1.0E-11 5.00E 4.00E-15 Strontium 99 1.0E-11 4.17E 4.95E-13 Molybdenum Cesium - 134 1.0E-11 6.67E 8.4(E-14 Cesium - 137 1.0E-11 6.90E 7.34E-14 Cerium - 141 1.0E-11 8.02E 1.04E-13 Cerium - 144 1.0E-ll 3.01E 4.24E-13 Gross Alpha 1.0E-11 9.26E 1.07E-14 Tritium 1.0E-6 1.17E 1.21E-7 i
3 Page 13 ATTACHMENT 9 Lower Limits of Detection For Effluent Sample Analysis (cont.)
Liquid Effluents Required L.L.D.
Typical L.L.D.
Radioisotope (uCi/ml)
(uCi/ml) 1.11E-7 87 1.0E-5 8.38E-8 Krypton Krypton - 88 1.0E-5 1.51E 1.93E-7 Xenon - 133 1.0E-5 1.08E 1.38E-7 133m 1.0E-5 4.29E-7 5.37E-7 Xenon Xenon - 135 1.0E-5 4.56E-8 6.31E-8 Xenon - 133m 1.0E-5 7.92E 1.78E-7 Xenon - 138 1.0E-5 2.38E-7 4.34E-7 131 1.0E-6 5.12E 6.74E-8 Iodine 7.30E-8
)
Manganese - 54 5.0E-7 4 15E-8 i
1.00E-6 Iron - 55 1.0E-6 9.00E-7 Cobalt - 58
- 5. 0 E,7 2.86E-8 7.61E-8 l
Iron - 59 5.0E-7 8.90E-8 1.30E-7 Cobalt 60 5.0E-7 8.55E 8.88E-8 Zine - 65 5.0E-7 1.06E 1.19E-7 Strontium - 89 5.0E-8 4.00E 5.00E-8 Strontium - 90 5.0E-8 6.00E 2.00E-8 Molybdenum - 99 5.0E-7 2.67E 3.29E-7 Cesium - 134 5.0E-7 5.10E 6.41E-8 Cesium - 137 5.0E-7 3.15E-8 7.07E-8 141 5.0E-7 6.72E 9.89E-8 Cerium Cerium - 144 5.0E-7 2.96E-7 4.22E-7 Cross Alpha 1.0E-7 5.33E 6.18E-9 3.33E-6 Tritium 1.0E-5 3.22E-6
Tech, Spec. 6.9.1.9 VIItOINIA 1$LECTitIC AND l' OWE 11 COMI*ANY It t e nt Moxn, Vi no NIA 202G1 August 31, 1987 Vars Pammissant Ni etsam orunavions United States Nuclear Regulatory Commission Serial No.87-527 Attention: Document Control Desk N0/DJV:jmj Washington, D.C.
20555 Docket Nos.
50-338 50-339 License Nos.
NPF-4 NPF-7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT Enclosed is the North Anna Power Station Semi-Annual Radioactive Effluent Release Report for January 1,
1987 through June 30, 1987.
The report, submitted pursuant to North Anna Station Technical Specification 6.9.1.9, includes a so:rmary of the quantities of radioactive liquid and gaseous effluents and solid waste released during the previous six months, as outlined in Regulatory Guide 1.21, Revision 1, June 1974.
Very truly yours, d
W. L. Stewart Enclosure cc:
U. S. Nuclear Regulatory Commission 101 Marietta Street, N.W.
Suite 2900 Atlanta, GA 30323 Mr. J. L. Caldwell NRC Senior Resident Inspector North Anna Power Station FEYd
1 I
i i
1 A
ES 6 V n-d3S @.
S0-08N00 1
- - - - - - - -. _ _ _ _. _ _ _ _ _ _ _ _