ML20197D208

Monthly Operating Repts for Feb 1986

ML20197D208
Person / Time
Site:	Sequoyah
Issue date:	02/28/1986
From:	Dupree D, Wallace P TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8605140182
Download: ML20197D208 (109)

Text

{{#Wiki_filter:. ) A l TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT .1 MONTHLY OPERATING REPORT ~ TO THE NUCLEAR REGULATORY COMMISSION " FEBRUARY 1986" i UNIT 1 2 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 4 A#-- Submitted by: P. R. Wallace, Plant Manager 1

TABLE'0F CONTENTS I. Operational Summary Page a Performance Summary 1 Significant Operational Events 1 Fuel Performance and Spent Fuel Storage Capabilities 2 PORVs and Safety Valves Summary 2 Licensee Events and Special Reports 2 Offsite Dose Calculation Manual Changes 3 II. Operating Statistics A. NRC Reports Unit One Statistics 4-6 Unit Two Statistics 7-9 B. TVA Reports ~ Unit Outage and Availability 10-11 4 Nuclear Plant Operating Statistics 12 Reactor Histograms 13 III. Maintenance Summary Electrical Maintenance 14-18 In:trument Maintenance 19-24 1 Mechanica) Maintenance 25-27 Modifications 28-34 IV. Environmental Qualification /EQ) Sammary 35-41 V. Offsite Dose Caletlation Manual Change Attachments 1 thru 5 l

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Operations Summary February 1986 The following summary describes the significant operational activities for the month of February. In support of this summary, a chronological log of significant events is included in this report. '{ The units remained in an administrative shutdown the entire month due to documentation concerns relating to the environmental qualification of various { electrical equipment (10CFR50.49). Outage related maintenance and modifications are being performed. Unit I has been off-line 190 days. Unit 2 has been off-line 191 days. l Significant Operational Events Unit 1 Date Time Event l 02/01/86 0001C The reactor was in mode #5. The administrative ) ~ shutdown due to 10 CFR50.49 continues. 02/28/86 240Qf The reactor was in mode #5. The administrative shutdown due to 10 CFR50.49 continues. Unit 2 Date Time Event 02/01/86 0001C The reactor was in mode #5. The administrative s-shutdown due to 10 CFR50.49 continues. 02/28/86 2400C The reactor was in mode #5. The administrative shutdown due to 10 CFR50.49 continues. s i 1 1

Fuel Perforr.snee j Unit 1 The core average fuel exposure accumulated during February was 0 MWD /MTU with the total accumulated core average fuel exposure of 0 MWD /MTU. i i Unit 2 "I The core average fuel exposure accumulated during February was O MWD /MTU with the total accumulated core average fuel exposure of 8097.51 MWD /MTU. There were four shipments of cycle #4 new fuel (48 bundles) received during the month. All new fuel is presently stored in the new fuel storage vault. Spent Fuel Pit Storage Capabilities The total storage capability in the spent fuel pit (SFP) is 1,386.

However, there are five cell locations which are incapable of storing spent fuel. Four locations (A10, All, A24, A25,) are unavailable due to a suction strainer conflict and one location (A16) is unavailable due to an instrumentation con-flict. Presently, there is a total of 348 spent fuel bundles stored in the SFP. Thus, the remaining storage capacity is 1,033.

PORVs and Safety Valves Summary No PORVs or safety valves were challenged in February 1986. Licensee Event Reports The following licensee event report (LER) was reported to the Nuclear Regulatory Commission in February 1986. LER DESCRIPTION OF EVENT 1-86001 During a review of the surveillance instruction scheduling files on January 9, 1985, it was discovered that " Control Building Emergency Air Cleanup System Filter Train Test" l (SI-143) had not been performed within the allowable i technical specification time limit. This performance must be done once every 18 months. The method of scheduling this test was in error. Special Reports The following special report has been submitted to the NRC. REPORT # DESCRIPTION ) 85-07 On September 27, 1985, at 1000 CST, fire door A-131 was l opened to allow routing of an air hose for performance { of surveillance instruction " Containment Spray-Spray Nozzle Test," (SI-138). Door A-131 is the door to the unit 2 vent and purge air room at auxiliary building j clevation 714. This report was required per the Technical i 1 Specification 3.7.12. I 2 1 + 7 --e-c,, -,-n.-n.,.-n-,m._,g,,,. - - - - - - - -.. -, -. - _ _,, - -, w---, .--v--,- ,,.v,,

j 2 s Offsite Dose Calculation Manual Changes .I i Offsite dose calculation manual changes were finalized September 25, 1985. ~[ l A copy of the changes is found in section Five (V), Attachments 1 thru 5. i 4 e 't e e A ,b i f l T i a 1 e s i a 3 i

t 4 i a -n i 1 e. i j 4 l 4 1 ) i OPERATING STATISTICS (NRC REPORTS) 4 O 1 1 1 j b 4 k i u l 4 1 1 1 1 1 i

OPERATING DATA REPORT 4 DOCKET NO. 50-327 DATE MARCH 7,1986 COMPLETED DY D.C.DUPREE TELEPHONE (615)870-6544 OPERATING STATUS l 1. UNIT NAME: SEOUOYAH NUCLEAR PLANT, UNIT 1 NOTES: 2. REPORT PERIOD: FEBRUARY 1986 3. LICENSED THERMAL POWER (MWT): 3411.0 i 4. NAMEPLATE RATING (GROSS MWE): 1220.6 5. DESIGN ELECTRICAL RATING (NET MWE): 1148.0 l 6. MAXIMUM DEPENDADLE CAPACITY (GROSS MWE): 1183.0 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1148.0 l B. IF CHANGES OCCUR IN CAPACITY RATING 3(ITEMS NUMBERS 3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS: j 9. POWER LEVEL TO WHICH RESTRICTED,IF ANY(NET MWE):

10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YR.-TO-DATE CUMULATIVE d l

11. HOURS IN REPORTING PERIOD 672.00 1416.00 40897.00

12. NUMBER OF HOURS REACTOR WAS CPITICAL O.00 0.00 24444.91

13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00 14.' HOURS GENER ATOR ON-LINE O.00 0.00 23871.13 1

15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

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16. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 0.00 77060971.91

17. GROSS ELECTRICAL ENERGY GEN. (MWH) 0.00 0.00 2b?76386.OO

18. NET ELECTRICAL ENERGY GENERATED (MWH)

-2959.00 -6152.00 24936585.00 j

19. UNIT SERVICE FACTOR O.00 0.00 58.37 l

20. UNIT AVAILADILITY FACTOR O.00 0.00 58.37,

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 53.11

22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 53.111

23. UNIT FORCED OUTAGE RATE 100.00 100.00 22.05

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

) PENDING ASSESSMENT OF THE TVA NUCLEAR POWER PROGRAM DY THE MANAGER OF NUCLEAR POWER. t l NOTE THAT THE THE YR. -TO-DATE AND CUMULATIVE VALUES HAVE DEEN UPDATED. l ) 1 i ) 4

~ i SEQUOYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL DOCKET NO. : 50-327 UNIT : ONE DATE : MARCH 5,1986 COMPLETED BY : D. C. DUPREE ~ TELEPHONE :(515)B70-6544 MONTH FEBRUARY 1986 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL j DAY (MWe Net) DAY (MWe Net) 01 0 15 0 ) i 02 0 16 0 j 03 0 17 0 04 0 18 0 05 0 19 0 06 0 20 0 07 0 21 0 i 08 0 22 0 09 0 23 0 10 0 24 0 11 0 25 0 12 0 26 0 13 0 27 0 14 0 28 0 5

9 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-327 UNIT NAffE Sequoyah One DATE March 5, 1986 C0ffPLETED BY D. C. Dupree REPORT !!0NTl! February 1986 TELEPlIONE (615)870-6544 l l w o oyg Licensee gg go, Cause & Corrective N gg g 3g ygg Event gg gg Action to l Mo. Date o o y go g g g c: Report # go gu Prevent Recurrence

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o.c p u i c zmg l m l 7 851220 F 672 F 9 10CFR50.49, Environmental Qualification of electrical equipment important to plant safety. l 3tlethod: 4 Exhibit G-Instructions 2 Reason: 1F: Forced S: Scheduled A-Equipment Failure (Explain) 1-itanual for Preparation of Data B-!!aintenance or Test 2-!!anual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File D-Regulatory Restriction 4-Cont. of Existing (NUREG-0161) E-Operator Training & License Examination Outage F-Ailministrative 5-Reduction G-Operational Error (Explain) 9-Other sExhibit I-Same Source' !!-Other (Explain) 6 (* a

{ OPERATING DATA REPORT 4 ) DOCKET NO. 00-328 I DATE MARCH 7,1986 COMPLETED DY D.C.DUPREE TELEPHONE (615)870-6544 OPERATING STATUS 1 1. UNIT NAME: SEOUOYAH NUCLEAR PLANT, UNIT 2 NOTES: J 2. REPORT PERIOD: FEBRUARY 1996 3. LICENSED THERMAL POWER (MWT): 3411.0 4. NAMEPLATE RATING (CROSS MWE): 1220.6 } 5. DESIGN ELECTRICAL RATING (NET MWE): 1148.0 l 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1183.0 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1148.0 f 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS j 3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS- ~ l 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY(NET MWE): I

10. REASONS FOR RESTRICTIONS, IF ANY:

1 f j THIS MONTH YR.-TO-DATE CUMULATIVE 1

11. HOURS IN REPORTING PERIOD 672.00 1416.00 32857.00

12. NUMDER OF HOURS REACTOR WAS CRITICAL O.00 0.00 21984.54

13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00 I

14. HOURS GENERATOR ON-LINE O.00 0.00 21494.42 1

15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 3.00

)

16. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 0.00 69127977.22

17. GROSS ELECTRICAL ENERGY GEN. (MWH) 0.00 0.00 23536780.00 j

18. NET ELECTRICAL ENERGY GENERATED (MWH)

-3691.00 -6907.00 22625050.60 I

19. UNIT SERVICE FACTOR O.00 0.00 65.42

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20. UNIT AVAILADILITY FACTOR O.00 0.00 65.42 3

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 59.99 j

22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 59.98 1

23. UNIT FORCED OUTAGE RATE 100.00 100.00 23.15

24. SHUTDOWNS SCHEDULED OVER NEXT 6' MONTHS (TYPE, DATE, AND DURATION OF EACH):

l

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

l PENDING ASSESSMENT OF THE TVA NUCLEAR POWER PROGRAM DY THE MANAGER OF i NUCLE AR POWER. 1 I 1 l NOTE THAT THE THE YR. -TO-DATE AND i CUMULATIVE VALUES HAVE DEEN UPDATED. l l i i 7

9 SEQUOYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL DOCKET NO. : 50-328 UNIT : TWO DATE : MARCH 5,1986 COMPLETED BY : D. C. DUPREE TELEPHONE :(615)S70-5544 ~ I i NONTH FEBRUARY 1986 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (NWe Net) DAY (MWe Net) i 01 0 15 0 02 0 16 0 03 0 17 0 1 I 04 0 18 0 I 05 0 19 0 j 06 0 20 0 07 0 21 0 08 0 22 0 09 0 23 0 t 10 0 24 0 11 0 25 0 i 12 0 26 0 13 0 27 0 14 0 28 0 .I 4 I { 8

e UNIT SlIUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-328 UNIT NAME Sequoyah Two DATE March 5, 1986 COMPLETED BY D. c. Dupree REPORT !!0NTl! February 1986 TELEPIIONE (615)870-6544 s 5. u Licensee go, fe, Y y 'j Cause & Corrective N cg No. Date g 35; ygg Event gg g] Action to o g. go g ggc Report # go gu Prevent Recurrence u =v e o.cl

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n 10CFR50.49, Environmental Qualification of 9 850821 F 672 F 4 electrical equipment important to plant safety l l 2 3 4 Exhibit G-Instructions l 1F: Forced Reason: tlethod: i S: Scheduled A-Equipment Failure (Explain) 1-!!anual for Preparation of Data l B-!!aintenance or Test 2-flanual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File D-Regulatory Restriction 4-Cont. of Existing (NUREG-0161) E-Operator Training & License Examination Outage F-A.iministrative 5-Reduction 3 Exhibit I-Same Source. l G-Operational Error (Explain) 9-Other l II-Other (Explain) l 9 l

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tvA in2A (twoc su NUCLEAR PLANT OPERATING STATISTICS Sequoyah Nuclear Plant Period Hours 672 Month February 19 86 Item 6 No. Unit No. UNIT ONE UNIT TWO PLANT 1 Average Hourly Gross Load, kW 0 0 0 2 Maximum Hour Net Generation. MWh 0 0 0 3 Core Thermal Energy Gen, GWD (t)2 0 0 0 4 Steam Gen. Thermal Energy Gen., GWD (t)2 0 0 0 8 5 Gross Electrical Gen.. MWh 0 0 0 j 6 Station Use. MWh 2,959 3,691 6,650 E 7 Net Electrical Gen.. MWh -2,959 -3,691 -6,650 U 8 Station Use. Percent N/A N/A N/A 9 Accum. Core Avg. Exposure. MWD / Ton 1 0 0 0 10 CTEG This Month.106 BTU 0 0 0 6 11 SGTEG This Monta,10 BTU 0 0 0 12 13 Hours Reactor Was Crit # cal 0.0 0.0 0.0 14 Unit Use, Hours. Min. 0:00 0:00 0:00 15 Capacity Factor, Percent 0.0 0.0 0.0 j 16 Turbine Avail. Factor. Percent 0.0 0.0 0.0 17 Generator Ava't. Factor Percent 0.0 0.0 0.0 g ta 18 Turbooen. Avail. Factor Percent 0.0 0.0 0.0 19 Reactor Avail. Factor. Percent 3.0 0.0 0.0 6 20 Unit Avail. Factor. Percent 0.0 0.0 0.0 21 Turbine Startuos 0 0 0 22 Reactor Cold Startuos 0 0 0 23 y 24 Gross Heat Rate, Blu/h Wh N/A N/A N/A j 25 Net Heat Rate, Btu /kWh N/A N/A N/A ,E 26 C 27 g 28 Throttle Pressure. ps g N/A N/A N/A C 29 Throttle Temperature, "F N/A N/A N/A Q 30 Enhaust Pressure, inHg Abs. N/A N/A N/A g 31 Intawe Water Temp., *F N/A N/A N/A t-32 31 Wiq Feedwater, M Ib/hr N/A N/A N/A 34 35 36 j 37 Full Power Capacity, EFPD 404.86 363.65 768.51 38 Accum. Cycle Full Power Days, EFPD 0.0 210.8416 210.8416 j 39 Oil Fered for Generation, Gallons 4,092 2 40 Ort Heatina Value. Otu/ Gal. 138.000 _ 41 _Qgul Generation. MWh 62 d Man. Hour Net Gen. Man. Day Net Gen. Load MWh Time Date MWh Date Factor, % 3 43 N/A N/A N/A N/A N/A N/A Remarks: IFor BFNP this value is MWD /STU and for SONP and WBNP this value is MWD /M TU. l 2(t) indicates Thermal Energy. 5 m itAR.131986 G.k. M 'm D:te Submitted Date Revised NSW*PWr,5 Rh I

SEQUOYAH ONE REACTOR HISTOGRAM 110 100 - 90 - t;; So - m 70 - ~ 60 - b3 50 - 0 40 - O O 30 - 6 tr 20 - 10 - 0- -10 O 4 8 12 16 20 24 28 32 FEBRUARY 1986 SEQUOYAH TWO REACTOR HISTOGRAM 100 90 - 80 - h 70 - U 6 60 - 1 y 50 - 40 - (rO 30 - 0 20 - 10 - O- - :: -10 O 4 8 12 16 20 24 28 32 i FEDRUARY 1986 13

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12:24:11 03-05-86 ELECTRICAL MAINTENANCE MONTHLY REPDRT FDR FEBRUARY PAGE 2 DATE.... COMPONENT..... FAILURE DESCRIPTIDN...... CAUSE OF FAILURE......... CDRRECTfUE ACTIDN........ MR.ND.. PROPER MDTDR RDTATIDN. 86-01-31 1-CENB-082-000 DIESEL CEN. 14-4 UDLTAGE EXCITATION CDNTRDL TIME ADJUSTED MINIMUM-MAXIMUM 9105470 1A-A AND FREOUENCY WAS NOT DELAY TRIP CURRENT LEVEL EXCITATION CDNTROL TIME WITHIN TECH. SPEC. WAS DUT OF ADJUSTMENT. DELAY TRIP CURRENT LEUEL TD MINIMUM SET PDINT PER UALIDATED UENDDR MANUAL. 84-01-31 1-CEMB-082-000 UOLTAGE DID NOT FALL REGULATDR TRIMMIT ADJUSTED THE RESULATDR 8100409 1A-A WITHIN RANCE DF 10 PDTENTIDMETER MAS DUT DF TRIMMIT PDTENTIDMETER 1/4 SECDHDS. ADJUSTMENT. TURN. 86-02-04 0-NS-082-0165-ACTUATOR ENGINES HANDSWITCM NAS BAD DUE 10 REPLACED MANDSWITCH AND 8111744 A LOWER-RAISE-NDRMAL ACE DR CYCLIC FATICUE. CHECKED FDR PRDPER HAND! WITCH INDICATED DPERATION. CONTACTS MAKlWC UP INTERMITTENTLY. 84-03-04 0-NS-082-0225-ACTUATDR ENGINE 1 182 BY NANDSMITCH NAS BAD DUE TO REPLACED NANDSNITCH AND B111745 A 2A-A LONER-RAISE-NDRMAL ACE AND CYCLIC FATICUE. CNECKED FOR PROPER HANDSWITCH INDICATED DPERATIDN. CONTACTS MAKINC UP INTERMITTENTLY. 86-03-07 2-CENB-082-000 THE DIESEL HAS CIUEM A BAD RELAY CDNTACT REMOVED RELAY E3 AND B100862 2B-B BLACK DUT START SIGNAL CHECKED CDNTINUITY DN SI-7. THE CENERATOR ACROSS CDNTACTS DN PINS DNLY HENT TD A LITTLE 8 AND 11. CNECKED DUER 500 RPM THEN CDNTINUITY ACROSS STOPPED. NNEN STOP CONTACT 84 DN RELAY R1X. SIGNAL WAS CIUEN THE DPERATIDMS STARTED D/C WENT TD IDLE SPEED DIESEL AND RAN UP TD f THEN ! NUT DDWN AFTER 10 SPEED AND LDADED UP. MINUTES. 86-02-10' 1-2S-043-0071 LEAK TEST ISOLATIDN UALUE LIMITSWITCH MOUNTING STRAICHTENED LIMIT INITCH B105202 r w o 15 t t

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== X J N Q W X2 N W WE W N D X 6 > Em J WW W W W = QEW M W M W EE EM Q W u M W W D M h AW W WA = D C M W MM ZJ E M GM N W Q Q JR EW W C D M uuG W W QC CO Q MQ = D X &W M W ZMW QM Ok WW m W . J W D Q um Z m W W X W J M m W X WMX E W EQ m M M C C 4 EX WW M Z W E k W WaQ M k W e m W Q X 4W C X XQ QQX QW 2 k WW M J EW 2 2 2 W W W W Q M. A W Q = e WM J M E DO W C U J D Ok2 EQ C MM WW >XWMW Q C EWW WJ WQ X C DZ W D m G X d m NW W W D m m WW W M W n W 7 QWW JM g m M W XWJ M 4 JQ G O D N D ZO X JE W 3 mWW Z Q Zac 6 WE M LX H m W C m W Q W O MM M WWW D A M T M m O N e e N N O E Z N e Q 0 Q M N W I W. M 8 O M N e m Q t e w X Q Q n m e Q @ M e m N M e s I W X M I 8 m 9 Q N e Q R X G I W W WE W N O M J W I Q E E W M N m M M m e Q t 8 9 I M e 8 6 m mW Q9 MO O M N M MW M l -Q i m N M m Q m e T w b M N N N N N O M.. 9 I I B 4 I O T N N N N N N N.. W Q Q Q Q Q Q b W t E S 9 0 0 N C W 4 T M Q W W W M M m I

es* ** 6 MAINTENANCE sum!ARY (INSTRUMENTATION) l

? INSTRUMENT MAINTENANCE 1 UNIT 1 Completed Workplan 11726 which finishes the CVI modification to the SSPS logic and adds annunciation to the radiation monitoring block switches in 1 the cain control room. During performance of SI-298.1, condensate storage tank header pressure switch 1 1-PS-3-121A was found out of tech. spec. tolerance. No apparent cause could be detected other than instrument drift. PRO 1-86-022 was initiated and the l switch was recalibrated and returned to service. During performance of SI-197, a train B control building vent isolation occurred. Instrument mechanics were calibrating TS-311-5B in place. When the switch [ contacts closed, the isolation logic completed (PRO 1-86-024). Investigation and determination of corrective action is continuing. Completed the replacement of all reactor coolant system narrow range RTDs. This i work w:s performed on SMI-0-68-28 for qualified life replacement as required by 10CFR50.49. During performance of workplan 11896, an inadvertent cold overpressure mitigation system (COMS) actuation occurred. When power is removed from the RCS temperature loops, the COMS setpoint module was driven low enough to cause the associated bistables to actuate. PRO 1-86-029 was initiated and instruments were recalibrated to include lov limit provisions. This corrected the problem, and the unit 2 COMS will be recalibrated in a similar manner. UNIT 2 i Completed rework of unit 2 A PIDG lugs. This involved the replacement or over-solder of all PIDG lugs used on solid wire in CSSC circuits. This work was performed on SMI-2-317-25 to address the concerns of NSRS Report No. I-85-101-WBN (SQN). 1 Completed replacement of steam generator level transmitter 2-LT-3-174. This work was performed on IM1-145.7 and was necessary to satisfy 10CFR50.49 requirements for environmental qualification. l COMMON Performed reliability evaluation of Barton model 288A differential pressure switches used in CSSC applications. This was in response to NRC inspector followup item no. 85-45-01. The evaluation detected several switches as being unreliable and will result in eventual replacement. 1 Continued support for the environmental qualification (EQ) program. Major work l items included resolution of equipment deficiencies and verification of QMDS requirements for new EQ binders. Experienced considerable rework because of ] inadequate documentation on past maintenance activities and because new binders have entered the program. Current status on EQ verification indicates approximately 66 percent. complete on unit 1 and 68 percent complete on unit 2 and common. s f f T 19 ..J

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M M W W M E E W M > DW u W WW M mm 3 . mQ XWm .M W mX W E 6 X M X W X W X W D D 6uM O EmXm 6&OO6 M X Q W W W W M Q 2 Q M M W Q L QQW C W X 6W O&QWJkkWMX Q N O k X X b X bu6XM QummmmMAM 6&Q6&&Q 22 O sWM M M d M 9a M X J N H W X m Q A 6 3 X J J 6 6 m N O 4 J W J 2 G E 3 L W W M M D X D X XW D L M J 2 WW QW Z J m W M M M M MW N X M XM 2 Q D WO M W 3 QJ 3 M = Q 2 m Q Em

== J E M 6 4 M 6 6 Q = E u W Q W Q W d e u WG d k MQ M 2 4 X QJ CJ M =W W 8 W m W G WC 6 W O 6 W 6 DW 2 3 M Q D e Xmh 3 L NW W W u um Q M E W Q 6 M = E QW W M Zu X X WW 6 OZ M mW E Q N 6u M W D u MMX 6 O 4 2 X M X W TX W W Xm e Q W X 6 m i M G M 2 WM Wm QM M m X Q J WQ Q j Em a W W M X > W 6 E m C O E X Q J W Q W e M X Q M Z O m L OM m XM Q = XJ JW 6 MM A W WQ M 6 4 M M m a Wme m L Q" E MM M um J Q W W W CM 6 k E 6 J m W2 W 'I .D E J O D M MTm um um u W W E E E 6 E > E M X M Q ES QW Q 40 4 E Q X Q Q QQ M 6 M W 4 W Q M J Q QX2 EM L Q J E X E M M M&M Q m J GM M ZM uk X m QW E W k J m = A E W 6 k M W J e W W E X W Q QS MM WW E m E 6 0 X X W mQ W M D 41 X Q = M u W = = X 2 = QM E E X NE X DD R n J E E u 2 .= wmu I Q g = E I 2 = = m 3 E e uW O 33 = = =X X M X OX O M => OMO I O Q

• W

= 5 W X 6 = G B 8 B C G = MS O6 cm B m W W a Th ob l > I eM Q m W X m N mE 2 e = mN N 6 N D m NJ N N E N N u O X W QM T m SQ t W 8 E mW D Q C M k M QNm M M X = Q N N M M WmNWm>mm T 4 mud I W I W M J 8 O u 8 m MW e 8 8 mW 8 M O T6 T4 e Z T e mL mm e MM t m m W M W e N .N Jm m Ouca em O Xm O Q O m>> OmmzT WQ 4 WQ9 E J O X2 8 = D 6 9 0 QC QM QQO JJ OM W 2 0 w W Z Q M QW O OQ Q M X >X O W X Q 4 A 6 X QMk e SO M M M L R C e D I T M t N6 M G M e kW 6 M I M u um i W W DJ 8 M M 6 u EM W W6uMM MM ON W N M ED D N > >M M E = Q& L W 3>>m E M MG h a 6 6 XM J O Z D ZW W M k 2 J JW JW JJ ZM Q EuJ J B E W m m e t X e NC 4 DM e X e 3 3 XD 4 O D E a & S D e M M e W e Q R 2 O 46NS Nw N4WNJA Nm NA WWONMNM NC NJNbb NMMMO M e 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 e e e e e e e e e e e e e e e J N N N N N N N N N N N N N N N XW EW= 9 m e e m O M m w O n N g N p Q M M M 'M N N O Q M O O N O O X CW M Q 6 N N N N N N N N N N N N N N N EuO O O O O O O O O O O O O O O O W M N h e O O 6 O M T n N N e m u M M T m m o O m M p N N N M N T X M N M M N N T N O M M M M 4 W m Q X M k W Q 6 Q D X 6 = 6 e N b N M N e m M N M m M M M E 9 4 9 O T T T Q O O Q O e M M Q Q O O O O O Q Q O c Q O O m X u X X X W X 6 6 6 O u 3 I C o w u u m N N E N w = = u u W 3 6 6 6 6 W Z E 2 J J d E J I k> N N N N N N W N N N N N N M O M D Xm M n 4 e T e M N e O M m T p W E 4 e e W D 4 M M M T T T T e G e e e e e T n N m m m m m e u O O O O O N N N N m m m m m V O O O O O O O O O O O e O O O M M M M M M M M M M M M M M M M E G S E M n M M M E O O O

1 e i v ~ 1 e Q G W X . N M m M O 2 Q uW M Q X W X W u 3 W J Q C Z W X M W W O um Q W = um J J J W u Q M N D M W G J W D W W X Q M W W Q W G W W J D W 6 6 W X E m W W W W W E 6 Q J W M G M 6 Q E Q Q m J Q W O = u = W W X J W W WW D J W W W M X Q W J M W H mmZ k E M N N m M J X D D uW E Q Q M X D = O M C J W W k m D m 6 W W Q W 4 W W C D X J O W QW O M W 4 W Z QD D J W G Q M W uw E X J X d = W Q W C W G A C MW M M Q Wu QM J C O k W M Q u u 4 X W C 6 J Ch 4 W m W W .W W C' = Q 2. Q Q4 bW A u X J m MM Z W G 4 Q W W M M J C W* Q G 6 QM u X = 4 Z W W W G Q W W = M Q W M m M W Q L W W D W u X J W 6 W Q E . X W W E 6 W W J W C E u X 6 M k W m QM DD 2 W W E u Q X WW M W M WW J Q W N G W C W W M m W W W Q u L. W W E W X u m Z l M Q uM Z E M D W X Z m W D W M Q U D M W Q E u QJ Q Q D E M J N 1 6 M m J X W W cme D 6 W m X W C u W J C HN M M W X M G C M WG M X u Q W m W W W W W 2 W W Q CW @ 2 W Q W mW M Q MuuH A Q M M . M 6 M4 Q NJ W M X uM M X W W W W D T X ZW E m X Q 6 Q W D D Q Q M mn M u X M X Q C M to M W Q Q 4 M4 E Q Q E C X C G W u Q C C E M X N C3 6 C m u ump s uM M m m D W M M g 12 2 E cm D M m W G W W X W X D W O N N W u .= E W W = G W 4 4 WL N N C D W W W X D Q G W QW J D J 6 J b 2 u X m W 6 X m2 W W EQ um WQ W 6 W GQ W G W m W W 6 AMW E Z M Z J W C J X & J O W G M W m c 2 = 9 2 X M =A W m Q W > = mm W m Q D W X X C W 2 H e M Q h u. s W Q J = Q M W M uu u m W J Z NW D X C = X C M M 6 m M M J W W D wmM Q ZQ > 6 WQ m6 NJ m E Q >J G m = D Q Z W u W W G 4 J Q W A M Q u MG W WX Q MA W 6 CE N N 3 W N E X 4 M J M 6 mQ W WQ M m.=um Z4 Q M LX M D Q m Q X Z G V. W E W EM m O w W C W u M C J W M QW WW D 2 JO W W Q W JW E NN O m N 6Z J L Z X M m E m M W Q EW E m M u ZX M Q M T M N M I m 2 E 2 O m M m m D 6 XW Z W E uh M N T uf 3 Q Q = X Z = > m mM W M M W WM WN W E N J uM M M W O 2 X MXM C m M X W M. X J Q d u um u j m N W um W L X W E W G W QJ G mW CC G Q 6 6 W 8 Q uM W M Q m M E Q E 2 EW L 6 M E W WW WE J W J Q J Q W Z W Z G M W W M D W E 6 W DW J Qm E EN EW b 4 m m AW AQ D W W Q Ek 2 W X Q Q X = uM 4N wm W M W W W X Q A u a E C W X W u M Q u 2 E = A t M E Mm M i C E Q C DWMW W uM E M m Sm uX W OM E SW m = X = E = n W W E W = uum D e = WXZ => M u Xm X e W W 8 Wu 9 Xu l Q M =

M I W W

0 W Q t =m 2 g 6 m = 6 N O Q = N O W C WW C 4 e i C D Z 9 m =X C . 9 6 uM M 8 S M T M WOW M m2 O X M m M T NM N QuT Q I m ch4 W m Tm 6 N D W 6 N>Wn N m N m N O X W N mm M M n Q n Q JnD m N62 Q TM O t C W e JW I m W e Q J N N N WN M W W M M M Q m mm M e 6 mmuca mecmaQ m m d e e o e W u e e e m e D e MOW e em QW Q 3 gcxw ggg g 6 3 g - O O X Q= W O O N QQM SoumcM 6, mu W QJ Q O Q u. M O Z e M CmX D b m n M D C W X 4 EC m QW W Q e 6 HQ e . M e e m UC Q CQ Q quo O . C X Q We4C M e mea XmW E X mm X M m X M M e e M e 2 M e X I X e M e m 6 Z M e M w . M mmm 6 8 u M 6 N em 6 M C m M uC W WW WW E T Q T Q Q M ONM W JnNmM N md N 6 u E E EuC E M W W W W m2 u m.m X mE L 6 M X J >JW WWM mbu 6 2 36 6 T X 0 C Z e q Z C W W 6 e Z 6 Q Z e = s e d e Q e E d Q t M E C M I X X W e W W W M t M X t M X e D Q M W NON EM NJM ocmN UNQ EM M M auM M M M WND Q M mMmq Nmq N M W 4 4 4 4 4 4 4 4 4 W m e m W W W W m W W W e M M J N N N N N N N N N N N N N N Z N w m m n a n m M T M N N N > L W N N O M M M M M M M Q Q Q Q X E W N N N N N N N N N N N N N N Q Q G N N N N N N N N N N N N N N EuQ O O O O O O O O O O O O O O T N 6 T m n C e 6 N O O O O W N m N n Q W O n T T M M C M ) u M X M N N M N o o M N N N N N 6 W M M M m X M W Q W Q X 6 a M C C O O O N O m W O m m m m E m m m n o m T T T T M Q Q Q Q Q Q Q Q Q Q Q C O O X u X X X X W X e 4 6 6 E D E E E k E M E F E O N N N N D 6 M M k k a A m J b Z Z Z Z MW W N N N M Q N N M M N M N N M D Xm E N T m N N w w m N M e m O M E M m m T Q N n n e N N e m Q n n n n n e w w w w 4 9 u. T T T T T T T T T T T T T T O O O O O o O O O O O O O O W M M M M M M M M M w M M M M E M d 6 m m m m m m m M O M

= e = e ~ 1 W 2 Q 2 u M W Q Q W Q M = u X a Q m = q D Q M C C Z X 3 D m a J W H J 6 Q Q W W W W W m W b Q M X X M Q M M c m W W D M Q Q 3 6 X E b M W J W W 7 C Q X m M M M D J Q J = m D u W C J J C D m u u. J . W = W 7 S q q u mC W W W a X XX J Q Q M p W Q W G W C QEJ W H M W k 6 2 m J u 6 W 6 E MM X m C D m J Q M Q M M 4 Q. Q. W W 3 > q W J E W = M W W m E M W G sm Q m e. M W e m mW W W D E = 4 G 6 M. W CQ WM W M M M J M 7 m X J D X X J X m uW M 4 C D Q a O M W W m m J m W M C m& W W 7 C X 2 a u M m a um 2 Q W H H Q 2. uM W X XX Q g M W W MOW N C =. Q Q 2 O W. m C m u W 26 = J XEM M MW m = N O A X Wm QWuaQ W W W 6 E X D D CmW j m X Q u 6 X M 6 T 6 Q uu O CX . W W N E CJ M W Q W O Q Q X M M W N E CQQ D u 6 > m X D O N X M D C W X W X X W W . ) G W QW O M QW QM MO CW D OM X W W W W D M D Q M u M uW M M M QW D j O mW O p X W M M D M M 6 7 W m D M M W E X 6 M D C O DW OM Q2 2 E E Q ) D J Q C G Q .M uC2 wmQ QW Q Q C j m W W X uW = Q 2 M O 6 W W 2 X M M M W M E W W Q W W W W W Q W M W M M Q Z W W Dm W m Xw m C C 6 m M cW Q W W M M M W MuC OU uuM D D J J Qm W J X W W. N N . W M m .A uM 6 4 X C D Q Q D D M M Q W X X X U D W X W Q W D W W E C E W X X G U W A Q Q J J G Q Q X Q EQ mm Q-C EQ W Z 6 2 4 W G Q W W Dm T u a b uX X X m uMX A 2 X M uM E M u u ks k u 4J M W Q N M m O W N G m 2 6 6 M m M Q Q Q i W J Q Q Q W Q D C Q X W W W W l 4 4 J E M u 6 W W G W W Q j hm W W W W X T WW W W W 6 M M M M L E u u 2 3 W W H OW E D D M W W M M M 2 h 2 X C Q W E W XM W Q Q J J W O W W Q W C M C M M Z Q ZW D E M M M 6 6 W C W N J N E W E W Q u m W m W C Q C W 4 A m mumu W m w mu W W X J J E M X Q Q m Q m E m C QWe m Q Q q q WJ > N Q X 6 36 D c2 W W X M C W X X W W W 6 m 6 N = G ammmL M X G D MM E a M M - Om W W W W 6 X M m C U N Q J J D W W M k W uW bM LM Q J XuM M M J J Q R E W X W W W X > W Q u m W B E m m Q M M DG D Q = DC W6 W6 2W W Q m 2 2 E N. O c w X b uZ QZQ bH E u M W d t M M N M m M J => m M M M 6 M M MO E M G M M e W C W W W W C 6 W M G E m M G Q E N X X Q Q E M U D M D D X 2 h a EXU S M Q W W Q S E E M M k W a J W XQ X QQ W M W W W M W M m = M m = = E W AQ W e J U W D = m Ku M 6 C CM W D E X A M i t X Q X 6 m e m W M E M M M M W X W M W J W W = W Q Q X O N E X X e 2XX m D C D C am D M M umM U I-u E E S u M M

=m W m Q 2 O 2 = M Q W =

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= W X Q Q G M G M C MW

• W =

= 8 3 W W m 0 C A W M 8 0

N e 4 C h m m O I a s u t oma =W = qud M N Q m u e m N mmmwag M e Q X. J XN W OM OM O uW G X 9 W XW D N W Q O M D T 74 7nQg mc C M J WW @ >O W m B N QMM O M O Q M Q M M M 6 M NQ Q WMN uN N WM 2 4 M m M m X M M m OW O W O Q I = m e e W t W 4 > q e C m e W . Em N Q t 9 0 Q e a e 4 e = e W E CM O Z O ZN= mm o mmWDEM M O O mz m m mM mma . J mQ m>>W m Q W W 4 OQ R e m m W D CW CW O b c = W m N G O X O O C 6 Q u M Q X N OW mX Q O Q Q C =O =c Q QS W ex e s LS e n 6 m W 3 a AD e Q L9 W Q m2 e M e M e 6 6 D # D e m e W W 6 W M CM J EM EM M M W J M C M uM M X Q D EuC uE W QW Q E NE X E M N mam% mwM W X E m M A X u a M mW W W W 2 6 X 6X J J Aa C W 6 6 e m 4 m a m l W C e W G Q 8 Q Li m M t W 9 2 0 Z I Q 4 Q e Q t W e N M i D Q h mO 2 MMM M NH M MM NW MXT &m NE mum uNE MU M uM mMm e i M 4 4 4 4 4 W 4 4

• O e

e m m m e e m W W W m m m e J N N N N N N N N N N N N N N N W E W. 4 T T m m W O T M C M = m C M M Z O O O O O N M M M M N N N M M X E W N N N N N N N N N N N N N N N Q Q C N N N N N N N N N N N N N N N E ue Q Q O O O O O O Q Q O Q O O O W N W O m q M m u W p N q E u M M n w O g M M o o m W M w T X H N N N O N N Q Q m O O W 9 6 W O M N M M N I M M X M C N M C Q W Q X T 4 Q N M M X G M O O m 6 M O O O N m m O O m m m m m K m m m m O m e m e O O O O M Q Q Q Q Q Q Q Q Q C O Q Q Q Q X U M W X E D E E E M W M M M E E W E E D 6 k k k M A M E W W W 6 6 J J W e O M M N M N M N M M N M M M M M 3 X m N T p N O e p e N m W W N m T E T C O m T N M n 4 m T T T T Q N Q Q Q O M e e w 4 e e e e u. n N N N N N M m m m m m m m m O O O O O M M M M M M M M M M E M M M M M M M M el M M M M M M K M M G M M M M M h

e 9 e- ~ L a. LaJ X X C2 C:3 X >= U = 6 O X tad 6 baJe D E

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f"1 >= E e== e4 E CW EO t> u T. M Q T e-o X X e O 6 >= C C3 h"3 M 6 L1 M M W me EK W 8 % bed W X CB O =J u Lee CD Ea O.4 6X e-4 6 E bed G E W bJ M W Mlt =6 en =6 m I C3 e C3 M Ett M ea ts t D >= bad DE O C3 LaJ e C2 >= e m 2g X em u m GC M = thE XM C E 6 6 eM 6 had ERC C3 Du D J had m e X e >= >= m ga== e4 LaJ >= O

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3 ta= hs. L M M>= N M bp M S N X h= o== E tfl 4 ED E T T sa G.o M W 48 m av'n 6 e4 og

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S 6 m* 9 MAINTENANCE

SUMMARY

(MECHANICAL) S 1 l l

MONTHLY REPORT FEBRUARY 1986 i MECHANICAL MAINTENANCE COMMON ]. 1. COMPLETED WORK ON IB CONTAINMENT SPRAY HTX. 2. COMPLETED WORK ON AUX. BOILER B, PLUCGED 6 TUBES. 3. WORK ON 0-FCO-31-488 AND 499 COMPLETE. 4. WORK ON 0-FCO-31-404 COMPLETE. 1 5. COMPLETED WORK ON 0-RM-0-206B. i 6. COMPLETED WORK ON 0-FCO-31-493. 7. REBUILT ACTUATOR ON 0-FCV-65-47A. 8. WORK COMPLETE ON 2-STN-26-1063. 9. COMPLETED MONTHLY AND QUARTERLY INSPECTION ON 2AA D/G. 10. PERFORMED MONTHLY PM ON SECURITY DIESEL. i j 11. REPLACED DIAPHRAGM IN 0-VLV-12-32. 4 i i

i i.

-25

l MONTHLY REPORT FEBRUARY 1986 MECHANICAL MAINTENANCE UNIT 1 r 1. COMPLETED WORK ON NOZZLE COVERS. 2. REPLACED VANES IN 90-100 RAD. MONITOR PUMP. I l 3. RAN SI-107 ON ICE CONDENSER. 1 4. COMPLETED WORK ON 1-FCV-1-181. i i 5. COMPLETED WORK ON 1-MVOP-67-131. 6. VERIFIED TORQUE ON 1-VLV-62-1053. 7. COMPLETED WORK ON LOOP 4 RTD MANIFOLD. i 8. COMPLETED WORK ON 1-MVOP-67-133. 9. REPACKED l-FCV-62-74. 10. RETORQUED REACTOR COOLANT PUMP FLANGE. t 11. REPLACED DIAPHRAGM IN 1-FCV-1-7. j 12. COMPLETED WORK ON LOOP 3 RTD MANIFOLD.

l 13.

REPLACED SOLENOID ON 1-FCV-62-69. 14. WORK COMPLETE ON 1-MVOP-67-142. 15. REPACKED VALVES 1-PCV-1-5, 12, 23, 30. l 16. WORK COMPLETE ON 1-MVOP-62-9. 17. INSPECTION COMPLETE ON 210 OF 264 SNUBBERS. i 18. STROKED STEAM DUMP VALVES. i I 1 26'

MONTHLY REPORT FEBRUARY 1986 MECHANICAL MAINTENANCE UNIT 2 t 1. RETORQUED BONNET ON 2-VLV-063-641. ~ 2. RAN SI-158 ON 2-VLV-70-92. i 3. COMPLETED WORK ON 2-FCV-65-52,,105B. 4. COMPLETED MONTHLY INSPECTION ON 2BB D/G. 5. COMPLETED WORK ON 2-FCV-65-5. 6. REPACKED VALVES 2-PCV-1-5 AND 2-VLV-72-502. 1 7. ALICNED 2B RFP. 8. REPACKED 2-PCV-1-5. 9 WORK ON 2A CONTAINMENT SPRAY HTX COMPLETE. 10. STROKED ALL STEAM DUMP VALVES. l 11. WORK ON 2AA BAT PUMP COMPLETE. l 12. REPLACED 0-RINGS IN 4A AND 29A MSIV SOLENOID VALVES. J 13. COMPLETED WORK.ON 2A RFP. ?- l 14. COMPLETED WORK ON 2-FSV-1-4A. 15. REPLACED SOLENOID ON 2-FSV-77-9. I 16. REPLACED 0-RINGS IN 2-FSV-1-22. 17. INSPECTION COMPLETE ON 688 OF 695 SNUBBERS. t 18. REPACKED 2-PCV-1-12. 4 J 4 i i 27 i

vw 9 e b MAINTENANCE SUl2fARY (MODIFICATIONS) ,_v.

. - _ = 4 S_UMMARY OF WORK COMPLETED MODIFICATIONS FEBRUARY 1986 i NUREG 0588 ECN 6032 - H2 Analyzer Relocation Work was completed. The final calibration will be done by Instrument Maintenance during startup. ECN 6231 - Remove Interferences Work is in progress on the unit 1 west valve room hanger. The Office of Engineering (OE) is continuing their reanalysis of unit 2 i upper compartment cooler ERCW piping. The preliminary indication is that one support may be deleted. 1 ECN 6552 - 0588 Solenoids All solenoids have been replaced. Some hanger work, painting, and functional testing remain. ECN 6561 - Modify Valve Room Doors and HVAC for Flood Protection The receipt of material has delayed the completion of this activity. The doors have been fabricated and are ready for installation. d ECN 6632 - Restrict Valve Room Flow Drains (Supersedes ECN 6609) l Preliminary work was begun to prevent the flooding of the auxiliary building because of water flowing into the building through the valve room floor drains. OE has not completed the ECN and USQD. i, APPENDIX R ECNs 5265. 5435, and 6343 - Fire Doors Work was completed on the first group of doors. The second workplan was placed in the approval cycle. The replacement of weather j stripping continues. ECN 6235 - Reroute Various Cables i Seven workplans are in work on conduit / cable reroute. Two workplans are in the approval cycle. Insulation is in progress at various locations. ECN 6305 - Elevation 714 Fire Barrier All identified work has been completed. I 28

e i APPENDIX R (continued) ECN 6311 - Operator Extension on PORV During postmodification testing (PMT), it was decided to add another U-j oint. This is on order and is scheduled to be delivered in early ' [, March. ECN 6315 - Replace Fuses Fuse installation has been resumed. ECN 6319 - Fire Protection Piping Final tie-ins and hydros are in work status. Tie-ins have been completed for elevation 734 and above. Work is now in progress on elevation 714. Work on elevations 690 and 669 will be completed in March. The installation of conduit and cable has begun. Additional work has been identified in the annulus that will require additional sprinklers and inside containment that will require sealing penetrations. OTHER ITEMS ECN 2768 - REVLIS Work has been completed. ECN 2783 - Installation of Fifth Diesel Six electrical related workplans for the fifth diesel installation have been placed in the workplan closing cycle. ECN 5009 - ERCW Piping Changeout From Carbon Steel to Stainless Steel Additional work involving the replacement of several small isolation valies has been added. The workplan was written and placed in the approval cycle. Some insulation activities remain incomplete. ECNs 5034, 5713, 5743, and 6064 - Various Platforms in Lcwer Containment Paint work continues. When this work has been completed, the grating will be installed. ECN 5202 - Interface of Fifth Diesel With Other Diesels Workplans for the interface of the fifth diesel with other diesels for train IA-A and 1B-B are in the approval cycle. ECN 5252 - Label Hode Voltages in Manholes No progress was made on this job this period; four manholes remain. 29

OTHER ITEMS (continued) ECN 5347 - Replace Doors C-49 and C-50 (Electrical Portion) This work is complete. ECN 5373 - Condensate Demineralizer Air Compressor Final PMT is in progress. ECN 5620 - Add Instrumentation for Auxiliary Feedwater Pump Work is on hold. ECN 5645 - Replacement of Flow-Control Valve 2-329 Insulation installation was completed. This completes all identified mechanical activities. ECN 5657 - Installation of MSR Drain Valves Reinsulation remains incomplete. Caps are being installed on the valve nipples. ECN 5667 - Double Isolation Valves for Flow Orifices (Unit 2) Work was started on the remaining eight flow elements. ECN 5703 - Reinforcement of Block Walls The current need for the wall was questioned by PORC. OE reviewed and determined that one wall could be removed and the second wall could be left as is if isolation valves were tagged closed. OE is rewriting the ECN and USQD to address these changes. ECN 5795 - Field Services Building Fire detection system work is on hold for materials. ECN 5914 - Improve Reliability of Steam Dump l Conduit is complete; one valve remains to be wired in. l ECNs 5938. 6305, and 6571 - Replace Feedwater Heater and Eroded Pipe The installation of insulation continues with emphasis on unit 2. Craft support for the PMT setup is continuing. Insulation for ECNs 6305 and 6571 is complete. Operations has begun flushing to clean up the unit 2 condensate system. All wiring is complete. Functional testing is in progress. ECN 6057 - Cable Tray Covers Approximately 240 out of 290 cable tray covers have been remanufactured or replaced. 30 L -

OTHER ITEMS (continued) ECN 6147 - Airlock Packing Nut Final testing of the airlocks on unit 2 remains incomplete. ECN 6196 - Pressurizer Hangers and Valves Work on unit 2 is complete for this time period. Unit 1 lacks cleanup, PNT work, and one support to complete. The three rebuilt ~ pressurizer safety valves with water trim valves have been returned from Wyle Laboratories where they tested satisfactory. ECN 6204 - Electrical Penetration Overcurrent Protectica Fuse replacement and fuse block installation are complete. We are awaiting a technical specification change to place the circuits in operation. ECN 6259 - Moisture Separator Reheater Tube Bundle Replacement Flushing activities are complete; insulation activities are incomplete. All conduit and cable installation has been completed. ECNs 6402 and 6439 - Pressurizer Instrumentation Relocation All work is complete except seal welding fill tees. This will be completed after Instrument Maintenance ~ completes fill and calibration. ECN 6417 - Install Alternate Seal Water for Pumps. CDWE Electrical drawings remain to be issued. ECNs 6491 and 6534 - ERCW Supports Work remains for one support. Paint work has not been started. ECN 6548 - Additional Support for Incore Drive Cart Work has been completed. ECN 6599 - Unit 2 Shield Building Anchor Problem The ECN and USQD were received; the workplan has been written and placed in the approval cycle. ECN 6601 - Removal of EGTS Backdraft Dampers We are awaiting the ECN and USQD from OE. Dry Active Waste Building (DCR 1898) Approximately 60 percent of the concrete foundation work has been completed. The remaining concrete foundation work will be done as weather permits. 31

D i i i OTHER ITEMS (continued) Weld Project 4 ~~ Support was provided for the weld project, Bechtel, and NRC inspectors reinspecting welds. I 1 I i .I 1 l i 4 i i i 4 32

MODIFICATIONS ECN DCR WI SYS SEQUENCE DESCRIPTION D1405 L X 036 12116 Remove existing pumps and install Milton Roy Milroyal Model DMRI-52-14 2SM pumps. Calibration chamber, and recirculation lines back to chemical tanks. D2024 L X 027 12914 Add permanent ladders to coolings to -WER lift pump motors. D2108L X 317 13070 Provide labor and materials to construct a flammable liquids storage facility to be located north of the new yard storage area on the north side of the Office and Power Stores Building. L5690 D1247 S X 001 11869 Modify balance arms on check valves to be done as needed. L6136 D19242 S X 061 12794 Fabricate and install ice condenser storage box at upper ice condenser landing el. 780. L6227 D0602 X 014 13351 SQ-DCR-602 MEB840821001, MED830902524, Modify the underdrains on the CPDS external regeneration tanks (AVION Tank AT), storage tauk (ST) receiving tank (RT) MOD 52. L6496 D0972 X 000 13518 Provide seismic mounting for limit switches on FCV-63-71 and FCV-68-308. L6504 D0972 X 000 13531 Replace limit switches for vlvs. 2-FCV-64-4 & 5 with environmental qualified switches. L6515 F3817 H 002 13523 Repair and modify CST per the attached sketches. L6522 F3851 H 001 13532 Replace the existing soft iron bonnett gasket with and new flexatallic gasket in viv. 1-511, 612 to reused furmantic leaks. 33 1 P '

MODIFICATIONS ECN DCR WI SYS SEQUENCE DESCRIPTION L6523 D0972 S H 000 13584 Drill 1/4" weep holes in junction boxes containing IE equipment located in the main steam viv. vault rooms and inside containment. L6525 D0972 S X 077 13546 Replace presently installed limit switches for the 77 system with qualified switches. L6547 D0972 S H 000 13576 Drill 1/4" weep holes in junction boxes located in areas subject to condensation formation following an HELB (High Energy Line Break). L6562 F3933 H 000 13562 DOC change only clear DWG. Discrepancies 1-MSH-3891-UNIH-140, 1-FDH-327 L6565 D0972 S H 000 13626 Drill two 1/4 inch weep holes in junction boxes located in areas subject to condensation formation following an HELB (High Energy Line Break). l L6567 F3965 H 079 13583 Remove the underwater light tracks irom the l reactor cavity and equipment pit. l l L6586 F4053 S H 400 13623 Allow 1/13 inch grinding on seal bar rather i than 1/16 inch that is allowed. Now change l detail on 3&4 cold leg to show actual con-l figuration. l L6594 F4054 S H 317 13624 Correct wiring error in JB 1414, JB 1407 l and JB 2795 L5194 D0781 S X 090 9282 Add wide range gaseous effluent monitors to monitor radioactive particles, iodines, and noble gases from the shield building j vent stack. L6171 F2469 S H 410 13096 Document on TVA drawings to clarify those doors that require lock guards under the new power l b}oc) concept per NRC rpquireppppp. 34 ei

~ ENVIRONMENTAL QUALIFICATION (E.Q.)

SUMMARY

i

Date: 3/5/86 0041E Estimated Date of Casoletion 50t No. Description ECN Engineer Workplan No. U-1 U-2 Comments EQP 8501 Disconnect 1-and 2-HS-62-61 6524 Peters 11901 C C U-2 QIR submitted. EQP 8502 Repla:e penetrations 23 and 48 6490 Peters 11001, 11802, C C Conplete QIR submitted. 11810, 11811 EQP 8503 Relocate RE-90, 273. -274 6500 Peters 11810, 11811 C N/A Couplete fleid verification sheets are in binder. No QIR needed. EQP 8504 Splice methods not correct N/A Stockton 80 MRs C C Conplete QIR submitted. EQP 8505 Drawing N/A N/A N/A N/A N/A EQP 8506 Seal containment isolation 6514 Kimsey 11880 C C Seals installed, new gaskets, valve top hat arrived 2/7, will install 2/9. EQP 8507 Rewire MOV N/A Rutledge 11866, 11853 3/7 C On U-1, all have been rewired; 114 of 115 have been functionally tested. EQP 8508 JB weepholes (press) 6523 Alas 11898 C C Complete QIR submitted. EQP 8509R1 Conduit seals 6529 Kimsey 11903, 11904 C C i EQP 8509R2 Conduit seals 6615 N/A No fleid work remaining. t EQP 8510 Disconnect local handswitches 6527 Peters 11901 C C EQP 8511 Submerged JB inside 6549 Peters 11901 C N/A containment 4 1 35 i ro

-m- ,4 --e.

---

u Date: 3/5/86 0041E Estimated Date of Conoletion SCR No.

Description ECN Engineer Workplan No. U-1 U-2 Conments EQP 8512R2 Rewire JB N/A Anburn 11855, 11856 3/10 C On U-1, 119 of 128 rewired, including EQP 8543. EQP 8513 Weep holes (moisture) 6547 Alas 11898 C C Conplete QIR submitted. EQP 8513R2 Weep holes (moisture) 6565 Alas 11937 C C Couplete QIR submitted. EQP 8514 Motor insulation 74-1, -2 6540 Branham 11906 N/A C Conplete QIR submitted. EQP 8515 Replace 2-PDT-30-43 6554 Legg 11912 C C Instrument Maintenance is calibrating. EQP 8516 Replace 2-LT-3-174 N/A Instrument N/A N/A 3/5 Need to FCR 47WB00-28 to delete Maint. Conax. EQP 8517 ABGTS humidity control 6578 Gonzales N/A C ABGTS B-8 conplete. EQP 8518 Submerged cables 6533 various/6 various 3/15 C 1 EQP 8519 Tee drains N/A Electrical N/A C C Conplete QIR submitted. Maint. EQP 8520 Expired cables 6553 Gonzalez 11902 C C EQP 8521 Delete TC and rework splices 6550 Stockton 11914, 11915 3/8 C EQP 8522 Rewire 1ccal panels N/A Stockton 11914, 11915 3/8 C EQP 8522R2 Rewire local panels N/A Instn ment 3/22 l Maint. l Page 36 1 ea

1 l Date: 3/5/86 0041E Estimated Date of Concletion SCR No. Description ECN Engineer Workplan No. U-1 U-2 Comments EQP 8523 Pilssing bolts and washers N/A Stockton 11914, 11915 3/8 C and misplaced brackets I l EQP 8524 Change setpoints 6551 Instrunent 11916 C 3/7 IM to transfer tenperature switch l Maint. from Watts Bar Nuclear Plant. EQP 8525 Reterminate hydrogen N/A Electrical N/A C C Conpleted by Electrical Maint. reconbiner (m) Maint. EQP 8526 Replace FSVs, U-l 1, U-2 11 6552 Mechanical 11897 C C Mods. EQP 8527 Coat TB, U-1 3, U-2 8 N/A Stockton 11914, 11915 C C (m) EQP 8528 Solder strain gauge Barton IMI Instrument N/A C C QIR suim:itted 1/24. transmitters Maint. EQP 8529 PDT-30-42, -43 6554 Legg 11912 C C EQP 8530 Gasket, Namco L/S N/A Electrical N/A 1/31* 1/24* 2 gasket and 2 mounting problems to (MR)

Maint, resolve.

• Reviewing all paperwork; will declare conpletion at end of review.

EQP 8531 Delete MOV heaters 6544 Rutledge 11866, 11853 C C EQP 8532 Delete L/S 1, 2-43-201, 6630 Alas OE revising ECN to reflect new -202, -207, and -208 proposal. 1 Page 37 i 1 1 e'

Date: 3/5/86 0041E Estimated Date of Concletion SCR No. Description ECN Engineer Workplan No. U-1 U-2 Conments EQP 8533 Delete dual voltage spilce N/A Rutledge 11866, 11853 C C EQP 8534 Resplice valve positioner N/A Maxwell MR C C Conplete QIR submitted. 3-174 and -175 EQP 8535 Replace limit switches, 6556 Stockton 11927, U-2 3/12 C U-1 10, U-2 12 11928, U-I EQP 8536 Valve room submergence 6561 Mechanical 11939 3/6 C Cap drains 6632 Mods. 3/31 3/28 OE to redo ECN to orifice drains. EQP 8536R1 Valve room submergence 66'12 Electrical 4/15 4/1 Cable will need rerouting. Mods. EQP 8537 Rebuild or replace JB 3078 6579 Auburn N/A 3/12 Foundanotherjunctionbox; initiated Category D FCR. When ECN is out, will write workplan to acconplish repair of both boxes. EQP 8538 Replace capacitors FCo-31-475, N/A Maxwell 11977 N/A 3/12 Capacitors delivered. Part -476 nunber discrepancy exists. Should be resolved by 3/8. EQP 8539 Replace capacitors N/A Instrtsnent 3/14 3/14 In work. Maint. EQP 8540 Replace pigtails to Target 6581 Maxwell 3/20 3/18 Material delivery to be 3/10; Rock solenoid valves purchase request 838756. 1 Page 38

l Date: 3/5/86 0041E Estimated Date of. Conv1etion SCR No. Description ECN En@eer Workplan No. U-1 ~ U-2 Consnents EQP 8541 Delete brakes 6582 Branhan 1120 3/28 N/A 1-rCV-63-93, -94. Brake issue resolved. EQP 8542 Replace unqualified cables N/A Hall Various _3/15 N/A Cables will be replaced in accordance with EQP 8518. EQP 8543 Replace JB wire N/A Auburn 11855, 11856 3/10 C t-1 status in EQP 8512R2. EQP 8601 Replace h, 2-PT-1-2A, -27A; 6588 Elkins 3/22 Will require replacanent. Transfer upgrade 2-PT-1-28 -27B from MIN in progress. Material-c._ _ delivery set fer 3/15. Upgrade kits have 5-to-7-week delivery. E is pursuing alternates. tyP 8602 Reroute control cables for

• • • • • • • • • • • • • • • " a " aaaaaa " aaaa " aA M
• No longer an issue.'

1, 2-FCV-70-87, -89 i-EQP 8603 Replace portion of PP7118 6627 Kimsey N/A 3/25 Will splice in Additional } Equipment Building and Elevation 759 Transfonner Room. EQP 8604 Cable 1PL3241A not qualified Aaaaa*Aaaaaaa"aaaaaaa"AAAA" "AAAaaaaaaaaaa M lenger an issue. EQP 8605 1-., 2-TS-74-43, -44, -45, -46 6589 Stockton 3/15 Replacement required. Material not qualified delivery due 2/24. EQP 8606 Undervoltage concern on 6611 Rutledge 4/15 Delivery of solenoids expected 4/4. feedwater isolation valve brakes Page '/9 1 l' 8

Date: 3/5/86 0041E Estimated Date of Canaletion SCR No. Description ECW Engineer Workplan No. U-1 U-2 Coments 1 EQP 8607 Delete TB for 1, 2-PT-1-2A, 6626 Instrument 3/22 Will wcrk same time as EQP 8601. -27A Maint. EQP 8608 Enable / disable MOV brakes 6621 Rutledge New item. Disable 8; enable 20. 6622 EQP 8609 Replace cable IV79738 N/A New item. EQP 8611 JB has weepiple in top N/A Ant > urn 3/6 WR written to repair. EQP 8612 Replace zone switches AAAAAAAAAAAAAAAAAAAaaaaaaAAAAAAAAAaaaAAAAAAAAA No longer an issue. 1 EQP 8613 Not yet received i EQP 8614 Weep holes in JB 4 I i 1 l i i Page 40 t t* t

l i Date: 3/5/86 0041E Estimated j Date of 1 Caeletion l SCR No. Description ECN Engineer Workplan No. U-1 U-2 Conuents N/A Move surge suppression netwrrk 5773 Kimsey 11883 C C U-2 couplete. On U-1, 1-PCV-68-340 4 for PORV in hold. Holding for maintenance to complete. EEB 8523 Penetration overcurrent 6606 Legg During closure process, it was i found that 6 circuits had not been addressed by ECNs. ECN 6606 j addresses this. N/A Work FCR to delete 1, 5883 Hall C C Need SI-166. 2-PS-3-160A, -1608, -165A, j and -1658 N/A Replace 1-FT-1-3A, -38, -10A, 6347 Instrument N/A 3/21 N/A i -108, -21A, -218, -28A, -288 Maint. l j NEB 8510 Relocate LT-68-320, 6439 Carrasquillo Various C C PT-68-323, -320 Peters Remount 63-71, 68-308 64 % Legg 11865 C C l Replace LS-65-4, -5 6504 Legg 11865 N/A C l MEB 8410R3 Replace LS-77-127 6525 Legg 11865 N/A C a Delete brakes FCV-62-61 6521 Branham 11905 C C EEB 8517 Replace pressure transmitter 6488 Branham 11931 C C PDT-65-80, -82, -90, and -97 l Pap 41 ? L 1 ?0

u 0FFSITE DOSE CALCULATION MANUAL CHANGES e n,

6 og CHANGES TO RADIOLOGICAL ASSESSMENT PROCEDURES (RAPS) ~ J- - FOR RARC APPROVAL RAP 1.1.1 IMPLEMENTATION OF RETS SURVEILLANCE REQUIREMENT 4.8.B.1 (PARTIAL) ~ FOR BROWNS FERRY NUCLEAR PLANT 1. Organizational changes implemented. 2. Format made to conform with RH/QA-3.1. RAP 1.2 IMPLEMENTATION OF RETS SURVEILLANCE REQUIREMENTS 4.11.2.2, 4.11.2.3, 4.11.2.4.1 AND 4.11.4 FOR SEQUOYAH NUCLEAR PLANT 1. Section 4.4 was added and reads, "It is the responsibility of the Air Quality Branch to provide TAS with meteorological data for the sequoyah area." 2. A sentence was added to Section 5.3 which states that if doses exceed 50 percent of the limit, TAS will obtain actual meteorological data (within 30 days after the end of the ^ month) and recalculate the doses. 3. Section 5.3 was changed to read that if limits are exceeded, RH will contact the SQN shift engineer by phone within one working day. A followup memorandum will be sent to the Plant I. Manager (with a copy to the Engineering Section Supervisor) within three working days. If the doses exceed twice the limit, the Plant Manager will be notified within three days so that doses specified in 40 CPR 190 are not exceeded. RAP 1.2.1 IMPLEMENTATION OF RETS SURVEILLANCE REQUIREMENTS 4.11.2.1.1. and 4.11.2.1.2 FOR SEQUOYAH NUCLEAR PLANT 1. Organizational changes implemented. 2. Format made to conform with RH-QA-3.1. 3. Added section 6.0 to provide assurance of QA provisions. RAP 1.3.1 IMPLEMENTATION OF RETS SURVEILLANCE REQUIREMENTS 4.11.2.1.I and 4.11.2.1.2 FOR WATTS BAR NUCLEAR PLANT-1. Organizational changes implemented. 2. Format made to conform with RH/QA-3.1. i i j' i

~ RAP 1.5 LAND USE SURVEYS 1. Organizational changes implemented. 2. Format made to conform with RH/QA-3.1. w 'a 3. Due to the move of the environmental monitoring function out of the Technical Assistance Section (Assessment Unit), all references to functions performed in relation to environmental monitoring were removed. This includes sections 4.1, 4.3, 5.1, 5.2, 5.7, 5.8, 5.9, and 8.2. 4. The end of section 4.1.1 was changed to read "those previously calculated following other surveys, and reporting results to the Supervisor of the Environmental Monitoring Section." 5. Section 5.3 was changed to read "Within 5 working days of the receipt of the formal land use survey from ERMI, the lead health physicist for assessing impacts due to releases of radioactivity to the atmosphere will be provided with copies of these formal survey results." 6. In section 5.4, the clause "and any need to prepare a Special Report to the NRC" was deleted. 7. In section 5.4.1, the time limit is changed from 20 days to 15 days. 8. In section 5.5, first sentence changed to read "The lead health physicist for atmoshperic pathway assessments will provide any necessary assistance to the lead health physicist for environmental monitoring of ERMI in preparing any Special Report required by Technical Specifications controlling formal land use surveys. 9. In section 5.5, the time requirement is changed from 26 to 21 days. RAP 2.2 IMPLEMENTATION OF RETS SURVEILLANCE REQUIREMENTS 4.11.1.2, 4.11.1.3.1 AND 4.11.4 POR SQN 1. Section 5.3 was changed to read that if limits are exceeded. RH will contact the SQN Shift engineer by phone within one working day. A followup memorandum will be sent to the Plant Manager (with a copy to the Engineering Section Supervisor) within three working days. If the doses exceed twice the limit, the Plant Manager will be notified within three days so that doses specified in 40 CFR 190 are not exceeded. RAP 3.3 IMPLEMENTATION OF RETS ADMINISTRATIVE CONTROL 6.7.3.A FOR BROWNS FERRY NUCLEAR PLANT 1. Organizational changes implemented.

s 2. Section 5.1 changed to read: Within 30 days after the end of each calendar quarter. Radiological Health Technical Assistance Section should receive information regarding BFN plant operation for the

• - e preceding calendar quarter. The information should cont 2in the following data:

^ ~ (a) Activity (Curies) released of each radionuclide via liquid and gaseous pathways. NOTE: Any activity reported as a less-than value should be considered to be zero for input to dose calculations. For those nuclides considered as parent-daughter pairs in the dose calculation, the maximum release will be selected from each of the pairs and entered. If the parent-daughter combinations are reported as a pair, the reported value will be entered into the dose calculation as the activicy of the parent and of the daughter. If the above information is not received within the i prescribed time, or if incomplete, the Engineering Section (Chemical Unit) Supervisor at BFN will be centacted directly for the information. ~ 3. Section 5.2, sentence added "This information will be provided by Data Services Branch." 4. Section 5.3, sentence added "This information will be provided by the Air Quality Branch." RAP 3.4 IMPLEMENTATION OF RETS ADMINISTRATIVE CONTROL 6.9.1.9 FOR SEQUOYAH NUCLEAR PLANT 1. Organizational changes implemented. 2. Format changed to conform with RH/QA-3.1. 3. Section 6.1 changed to read: Within 30 days after the end of each calendar quarter. Radiological Health Technical Assistance Section should receive information (SQN Surveillance Instructions 422.2 and 423.2) regarding SON plant operation for the preceding calendar quarter. The information should contain the following data: (a) Activity (curies) released of each radionuclide via liquid and gaseous pathways. i a 4 e

NOTE: Any activity reported as a less-than value should be considered to be zero for input to dose calculations. For those nuclides considered as parent-daughter pairs in the dose calculation, the maximum release will be selected from each of the pairs and entered. If the parent-daughter combinations are reported as a pair, the reported value ~ will be entered into the dose calculation as the activity of the parent and of the duaghter. If the above information is not received within the prescribed time, or if incomplete, the Engineering Section (Chemical Unit) Supervisor at SQN will be contacted directly for the information. 4. Section 6.2, sentence added "This information will be provided by Data Services Branch." 5. Section 6.3, sentence added "This information will be provided by the Air Quality Branch." 6. Section 6.4, the last sentence was deleted and a section added which reads: The total doses will be entered on SQN Surveillance ^ Instructions 422.2 and 423.2. If the calculated doses exceed the quarterly or annual ILmits specified in Appendix I to 10 CFR 50 and RETS 3.11.1.2, 3.11.2.2, 3.11.2.3, or 3.11.4, the shift engineer will be telephoned (within one working. day) with a written followup to the Plant Manager (within three working days) as to the level of the doses. The results (SQN Surveillance Instructions 422.2 and 423.3) will then be placed in a TVA interoffice envelope and sent to the Engineering Section Supervisor at SQN within 45 days after the end of the calendar quarter. 7. Section 6.7, changed to read: "A copy of the distribution correspondence, along with a copy of the assessment report, is sent to NUC PR RIMS as a QA record in accord with RAP 6.3." rap 3.5 IMPLEMENTATION OF RETS ADMINISTRATIVE CONTROL 6.9.1.9 FOR WATTS BAR NUCLEAR PLANT 1. Organizational changes implemented. 2. Format changed to conform with RH/QA-3.1. 3. Section 5.1 changed to read: G

q Within 30 days after the end of each calendar quarter, Radiological Health Technical Assistance Section should i receive information (WBN Surveillance Instruction 11.16) { regarding WBN plant operation for the preceding calendar quarter. The information should contain the following data: 'a _-.e (a) Activiv.y (Curies) released of each radionuclide via ~ liquid and gaseous pathways. ' 'q NOTE: Any activity reported as a less-than value should be considered to be zero for input to dose calculations. For those nuclides considered as parent-daughter pairs in the dose calculation, the maximum release will be selected from each of the pairs and entered. If the parent-daughter combinations are reported as a pair, the reported value will be entered into the dose calculation as the activity of the parent and of the daughter. If the above information is not received within the prescribed time, or if incomplete, the Engineering Eection (Chemical Unit) Supervisor at WBN will be contacted directly for the information. 4. Section 5.2. sentence added "This information will be provided by Data Services Branch." 5. Section 5.3, sentence added "This information will be provided by the Air Quality Branch." 6. Section 5.4, the last sentence was deleted and a section added which reads: The total doses will be entered on WBN Surveillance Instruction 11.16. f the calculated doses exceed the quarterly or annual :.imits specified in Appendix I to 10 CFR 50 and RETS 3.11.1.2, 3.11.2.2, 3.11.2.3, or 3.11.4, c the Engineering Section (Chemical Unit) Supervisor will be telephoned (within one working day) with a written followup to the Plant Manager (within three working days) as to the level of the doses. The results (WBN Surveillance Instruction 11.16) will.then be placed in a TVA interoffice envelope and sent to the Engineering Section Supervisor at WBN within 45 days after the end of the calendar quarter. 7. Section 5.9, added to read: "A copy of the distribution correspondence, along with a copy of the assessment report, is sent to NUC PR RIMS as a QA record in accord with RAP 6.3." 4

RAP 4.1 GENERAL DESIGN CRITERIA FOR ENVIRONMENTAL MONITORING PROGRAMS Deleted due to move of environmental monitoring to ERMI. RTP 6.2 ROUTINE ENVIRONMENTAL RADIOACTIVITY MONITORING REPORTS . _ o Deleted due to move of environmental monitoring to ERMI. ~ RAF 6.5 COOPERATIVE ENVIRONMENTAL DATA EXCHANGE PROGRAM Deleted due to move of environmental monitoring to ERMI. m. e a l a I e --s--. -er g -,se.

~. PROCEDURE FOR PROVISION OF METEOROLOGICAL JOINT FREQUENCY DISTRIBUTION OUTPUTS FOR LICENSED TVA NUCLEAR PLANTS TO THE TECHNICAL ASSISTANCE SECTION OF RADIOLOGICAL HEALTH _ J: 1. Purpose To describe the actions taken by the Assessment Section (AS) of the Air Quality Branch for the quality control and preparation of quarterly Joint Frequency Distribution (JFD) data for access by the Technical Assistance Section (TAS) of Radiological Health. This procedure will also be used for provision of monthly JFD data whenever requested by TAS. 2. Scope i 2.1 General This procedure specifies the steps that need to be taken between i the deadline for validation of onsite meteorological data by the Data Management Section (DMS) of the Data Services Branch for each quarter to the approval of Gaseous Effluent Licensing Code ~ (GELC) JFD output results by the AS for inclusion in the semiannual reports to the Nuclear Regulatory Commission (NRC). The steps to be taken pertain mainly to the AS but also reflect interfacing with the DMS, the Muscle Shoals Section (MSS) of the Computer Systems Development Branch, and the TAS. This procedure is reviewed and approved by the Radiological Assessment Review Committee (RARC). 2.2 Plant Specific When following this procedure, it includes two types of joint frequency distribution computer programs, the JFD and the Split JFD. The use of these two programs and their inputs differ by plant. The Split JFD program is used when both elevated and ground level releases are assumed, while the JFD program is used when only an elevated or a ground level release is assumed. The Split JFD program is run for Browns Ferry (and eventually Bellefonte) using: low level wind and low and intermediate level temperature a. i data. J b. intermediate level wind and intermediate and upper level temperature data. c. an effluent exit velocity of 12.6 m/s. l e i -__,,,_m.

The JFD program is run for: a. Browns Ferry (and eventually Bellefonte) using low level wind and low and intermediate level temperature data. b. Browns Ferry using upper level wind and intermediate and upper level temperature data. The disregarding stability q class part of this JFD product is the only part of interest. .~1 This product is used in the GELC program as "D" stability class input. c. Sequoyah (and eventually Watts Bar) using low level wind and low and intermediate level temperature data. 3. References 3.1 " Procedure for Implementation of RETS Administrative Control 6.7.3.A for Browns Ferry Nuclear Plant," Revision 3.3, TVA. i 3.2 Regulatory Guide 1.111 (Revision 1), " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," U.S. Nuclear Regulatory Commission, Washington, D.C. 3.3 Regulatory Guide 1.21 (Revision 1), " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," U.S. Nuclear Regulatory Commission, Washington, D.C. 3.4 offsite Dose Calculation Manual (for each TVA nuclear plant), Radiological Health, TVA. 4. Procedure 4.1 DMS notifies the AS that the quarterly meteorological data have been validated and are accessible. This step is scheduled to be accomplished within 25 days after the end of each calendar quarter. In addition, when monthly JFDs are requested, this step will be scheduled to be accomplished within 25 days after the end of each specified calendar month. 4.2 AS requests that the MSS prepare JFDs of wind speed and wind direction by stability class in the form of computer summary printouts, disk files of JFD output data, and hard copy of the data in the disk files. These are requested for each licensed nuclear plant. 4.3 When the printed outputs are received from MSS, AS reviews both the JFD printouts and the hard copy of the JFD programs output data stored on the disk files for accuracy and reasonableness. \\ 4

4.4 AS notifies TAS that the JFD output data disk files are ready to be accessed for input to the GELC computer program and provides a copy of the JFD products of step 4.3 to TAS, normally via remote printer in Chattanooga. This step is scheduled to be accomplished within 30 days after the c.nl of each calendar quarter. 4.5 AS files original JFD printouts and the hard copy of data from the JFD output data disk files. 4.6 TAS generates JFD sections as part of the GELC output and checks these for consistency with the AS JFD printouts. TAE then Provides the GELC output to AS for consistency for review of the JFD sections. 4.7 Upon verification of consistency, AS approves the GELC JFDs for inclusion in the smiannual report. 4.8 TAS is responsible for final disposition of the computer files of the JFD output data because the disk files will be overwritten with data from each succeeding quarter. a i r 1 ,i

f = t i o-QUALITY ASSURANCE PROCEDURES ~ ~ ' poa RADIOLOGICA'. ENVIRONMENTAL MONITORING PRESENTED TO THE RADIOLOGICAL ASSESSMENT i REVIEW COMMITTEES FOR BROWNS FERRY,

SEQUOYAH, MD WATTS BAR i

R SEPTEMBER 25, 1985 1 a i i I f i l i i i 1 i e i ,.-n.n.. .a.,. _. --..-me w,- .,,m.-----gnr--,-. .n- - -, -.~;+-----,,..

INTRODUCTION In order to fulfill the nuclear plant technical specification requirements concerning the responsibilities of the Radiological Assessment Review Committee (RARC), a review of the Quality Assurance program procedures related 'e to radiological environmental monitoring has been conducted. The review was tailored to the description of written procedures as it appears in Regulatory ~~ Guide 4.15 " Quality Assurance for Radiological Monitoring Programs (Normal '{ Operations) - Effluent Streams and the Environment," Revision 1. Paragraph C.3 reads, in part: " Written procedures should be prepared, reviewed, and approved for activities involved in carrying out the monitoring program, including sample collection; packaging, shipment, and receipt of samples for offsite analysis; preparation and analysis of samples; maintenance, storage, and use of radioactivity reference standards; calibration and checks of' radiation and radioactivity measurement systems; and reduction, evaluation, and reporting of data." Additionally, the content of the procedures was evaluated against the criteria for procedures contained in ANSI N18.7-1976, " Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants," to which TVA is committed. Specifically, the standard requires "Each procedure shall be sufficiently detailed for a qualified individual to perform the required function without direct supervision." The standard also states that "These procedures shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished." No effort was made during this review to critique the technical content of the procedures since this was determined to be outside the scope of this review. Each procedure was evaluated against the above criteria to ensure that quantitative and qualitative limits are prescribed where needed and that the required subject matter is covered to the extent ( necessary. PROCEDURES AND MANUALS REVIEWED In order to accomplish this review and to provide a basis for future reviews, it was necessary to identify those activities that must be controlled by written procedures, and to identify the manuals and procedures that implement these requirements. Because this review is designed to correct a deficiency identified by a quality assurance audit, those procedures that have been 1 previously reviewed by RARC, i.e., those related to offsite dose calculations have been omitted. ) The Sequoyah (SQN) and Browns Ferry (BFN) Technical Specifications, and the referenced Offsite Dose Calculation Manual, require that procedures exist for the following analyses on the listed samples. 4 l I

Gamma Scan: Particulates, rainwater, soil, surface water,' ground water, drinking water, sediment, clams, plankton, milk, fish, vegetation, fruit, vegetables. Gross Beta: Particulates, fallout, drinking water, plankton. uk _ 89Sr, 90Sr: Particulate, soil, surface water, drinking water, sediment, ~ clams, plankton, milk. 131 : Charcoal, milk. 1 3: Surface water, ground water, drinking water. H Direct: Environmental TLDs. The quoted description in Regulatory Guide 4.15 requires the following procedures: Sample collection, including scheduling, packaging, shipment, and 2 receipt; sample preparation and analyses; maintenance, storage, and i use of laboratory standards; calibration and routine checks for the measurement systems; data reporting, and evaluation. 1 TVA's radiological environmental monitoring program is described in the i Environmental Radinloqical Monitoring Manual (ERMM), which requires sampling and analyses in addition to those necessary for compliance with plant technical specifications. The ERMM also describes the responsibilities of the } organizations involved in radiological environmental monitoring. l Specifically, the ERMM indicates that Field Operations (FO) should have i procedures governing sample collection and preparation, and monitor calibration, maintenance, and repair. In order to review the procedures described by all of the foregoing, the following manuals, with the listed procedures, were examined. A set of tables cross-referencing required procedures to their designations and source manuals l 1s contained in Attachment A. 4 Radiation Dosimetry Procedures Manual ENVIR, R2 Environmental Dosimetry Procedures j Radiological Laboratory Procedures Manual Fe-01, R0 Radiochemical Determination of 55-Iron in Environmental Samples i G-01, R1 Gross Alpha and Gross Beta Activity Determination l G-03, R1 Gamma Analysis of Environmental Samples I-01, R1 Radiochemical Determination of 131-Iodine in Milk and Water

1-02, R0 Radiochemical Determination of 131-Iodine in Charcoal Pilters I-03, R0 Iodine-131 Activity Determination in Vegetation OP-01, R1 Operation of Low-Background Alpha / Beta Counting Instruments OP-02, R0 Sodium Iodide Single-channel Analyzer Operating Procedure ~}' OP-03, R0 Alpha spectrometer Operating Procedure OP-05, R1 Germanium Spectroscopy System Operatirg Procedure OP-06, RO Operation of Liquid Scintillation Counting Instruments OP-08, R1 Beta / Gamma Coincidence Operating Procedure I QASTD-0006, RO Instrument Logbook and Control Chart Maintenance QC-01, R0 Germanium Spectroscopy System Energy Calibration and Count Reproducibility Check QC-02, R0 Germanium Detector System Background Check QC-03, R0 Germanium Detecter Photcposh Resolution and Peak-to-Compton ~ Ratio Checks QC-04, R2 Gamma Efficiency Calibration of Germanium Detectors QC-05, R0 System Linearity Check QC-07, R0 Multichannel Analyzer Live-Time Clock Check QC-08, R0 Pole /Zero cancellation and DC Level Adjustments j QC-09, R0 System Noise Check QC-10, R1 Alpha and Beta Background and Count Reproducibility Checks QC-ll, R0 131-Iodine Single Channel Analyzer Counting System l Energy-Calibration, Count-Reproducibility and Background Level checks QC-12, R0 Beta-Gamma Coincidence Counting System Energy-Calibration, Count-Reproducibility and Background Level Checks QC-13, R1 Alpha / Beta Crossover Checks QC-14, R0 Determination of Beta and Alpha Counting Plateaus i 1 e

i QC-16, R0 Sodium Iodide Photopeak Resolution Checks QC-18, R0 Liquid Scintillation Background and Count Reproducibility Check 1 QC-20, R0 Alpha Spectrometer Energy Calibration and Count Reproducibility Check-QC-21, R0 Alpha Spectrometer Background Check QC-25, R1 Quality Control of Measuring and Test Equipment QC-100, R0 Calculation of Lower Levels of Detection for Environmental Analysis SC-01, R0 Collection of Environmental Monitoring samples SP-01, R0 Sample Preparation Sr-01, R0 Radiochemical Determination of 89, 90-Strontium in Environmental Samples STD-01, R1 Standardization of Carriers 1 i STD-02, R1 Beta-Gamma coincidence Standardization fot Iodine-131 STD-03, RO -Iodine-131 Single Channel Analyzer Counting System Standardization STD-04, R1 Handling of Radioactive Sources and Solutions STD-05, R0 Alpha, Beta, and Strontium Weight-Efficiency Curve Standardization T-01, R1 Tritium Activity Determination in Urine, Atmospheric Moisture, and Environmental Aqueous Samples Environmental Radiological Monitoring Manual Chapter 1, R3 Environmental Radiological Monitoring Programs for TVA Nuclear Power Plants Chapter 2, R3 Routine Environmental Radioactivity Monitoring Reports i Chapter 3, R3 Source Response Tests of Environmental Radiation Monitors l Chapter 4, R3 Identification of Anomalous Measurements l Chapter 5, RO Quality Assurance Provisions l l

ENVR-2, R4 Source Response Tests of Environmental Radiation Monitors ENVR-3, d4 Sampling Environmental Media ENVR-4, R4 Identification of Anomalous Measurements ~c u Field Operations NRE Procedures Manual S&P OPS-FO-NRE-41.1, R2 Collection and Handling of Samples S&P OPS-FO-NRE-41.2, R2 Water Sample Collection Techniques S&P OPS-FO-NRE-41.3, R0 Sediment Sample Collection Techniques Field Operations Instrumentation Manual, Volume 1 NR OPS-FO-NRE-61.1, R0 Servicing and Preventive Maintenance of Meteorological Equipment at Environmental Data Stations NR OPS-FO-NRE-61.2, R0 calibration of Wind Direction Sensor Climet Model 012-10 NR OPS-FO-NRE-61.3, R0 Azimuth Alignment of Wind Direction Sensors NR OPS-FO-NRE-61.4, R0 Calibration of Dewpoint Monitor EG&O Model 220 NR OPS-FO-NRE-61.5, R0 calibration of Dewpoint Monitor EG&O Model 440 NR OPS-FO-NRE-61.6, R0 Calibration of Raingauge Belfort Model 5915-12 NR OPS-FO-NRE-61.ll, R0 Calibrati;a of EDS Data Logger Air Temperature Channel NR OPS-FO-NRE-61.12, R0 Calibration of EDS Data Logger Wind Speed Channel NR OPS-FO-NRE-61.13, R0 Calibration of EDS Data Logger Solar Radiation i Channels NR OPS-FO-NRE-61.14, RU Calibration of EDS Data Logger Wind Direction Channel NR OPS-FO-NRE-62.1, R0 Servicing and Preventive Maintenance of Radiation Monitors i NR OPS-FO-NRE-62.2, R0 Calibration of ORNL Radiation Monitors, BFNP Only NR OPS-FO-NRE-62.3, R0 Calibration of ORNL Radiation Monitors, SQNP Only

NR OPS-PO-NRE-62.4, R0 Calibration of Tennelec Radiation Monitors, WBNP only NR OPS-FO-NRE-64.41. R0 Servicing of Water Samplers - Radiological Field operations Biological Resources Procedures e l Manual NR OPS-FO-BR-21.6, R0 Sample Collection - Zooplankton . i NR OPS-FO-BR-21.11, RO Qualitative Sample Collection - Benthic Macroinvertibrates 1 4 NR OPS-FO-BR-22.1, R0 Receipt and Handling of Biological Samples NR OPS-FO-BR-22.7, R0 Preparation of Asiatic Clams, Sediment, and Plankton Samples for Radiological Analysis NR OPS-FO-BR-22.8, R0 Preparation of Fish Samples for Radiological Analysis NR OPS-FO-BR-23.1, R0 Sampling with Gill Nets NR OPS-FO-BR-23.3, R0 Sampling with Fyke, Hoop, and Trap Nets NR OPS-FO-PR-23.9. R0 Electrofishing Doat Hvunted Unit DETERMINATIONS All aspects of the radiological environmental monitoring program, from sample collection by various organizations to review of the final analytical results and reporting to the NRC, are well documented by the procedures presently in place. Written procedures exist in the appropriate organizations for each required topical area. Further, errors or omissions, other than typographical, were not found, except for minor program description deficiencies in ENVR-3, R4, This problem had been previously identified by the responsible organization, and the procedure is presently in revision, with 1 the final draft scheduled for review by the RARC at the same time as this review. No actions by the RARC are recommended as a result of this review. b I i 1

ATTACHMENT A BFN Technical Specifications Sample Analysis Procedures Sample Type Analysis Procedure NOTE: All of these i Particulate Gamma G-03, R1 procedures are ^{ j Particulate Gross Beta G-01, R1 located in the Particulate Sr-89, -90 Sr-01, R0 Radiological Charcoal I-131 I-02, R0 Laboratory Fallout Gross Beta G-01, R1 Procedures l Rainwater Gamma G-03, R1 Manual Soil Gamma G-03, R1 Soil Sr-89, -90 Sr-01, R0 Surface Water Gamma G-03, R1 Surface Water Sr-89, -90 Sr-01, RO i Surface Water Tritium T-01, R1 Ground Water Gamma G-03, R1 Ground Water Tritium T-01, R1 Drinking Water Gamma G-03, R1 Drinking Water Gross Beta G-01, R1 Drinking Water Sr-89, -90 Sr-01, R0 s Drinking Water Tritium T-01, R1 Sediment Gamma G-03, R1 ~' i Sediment Sr-89, -90 Sr-01, R0 Clams Gamma 0-03, R1 Clams Sr-89, -90 Sr-01, R0 Plankton Gamma G-03, R1 Plankton Gross Beta G-01, R1 Plankton Sr-89, -90 Sr-01, R0 i Milk Gamma G-03, R1 Milk I-131 1-01, R1 Milk Sr-89, -90 Sr-01, R0 ) Fish Gamma G-03, R1 Vegetation Gamma G-03, R1 Fruit Gamma G-03, R1 Vegetables Gamma G-03, R1 l TLD N/A ENVIR, R2 (DOS-3) i i 1 I i l i b l

SQN Technical Specifications Sample Analysis Procedures Sample Type Analysis Procedure NOTE: All of these 1 =- Particulate Gamma G-03, R1 procedures are Particulate Gross Beta G-01, R1 located in the ~ __ Charcoal I-131 I-02, R0 Radiological Surface Water Gamma G-03, R1 Laboratory Surface Water Tritium T-01, R1 Procedures Ground Water Gamma G-03, R1 Manual Ground Water Tritium T-01, R1 Drinking Water Gamma G-03, R1 Drinking Water Gross Beta G-01, R1 Drinking Water Tritium T-01, R1 Sediment Gamm'a G-03, R1 Clams Gamma G-03, R1 Milk Gamma G-03, R1 Milk I-131 I-01, R1 Fish Gamma G-03, R1 Fruit Gamma G-03, R1 Vegetables Gamma G-03, R1 TLD N/A ENVIR, R2 (DOS-3) ? 0 m

Sample Analysis Procedures Required by Environmental Radiological Monitoring Manual (but not plant Technical Specifications) t Sample Type Analysis Procedure Plant NOTE: All of these ~ - _== - ~ Particulate Gross Alpha G-01, R1 BFN procedures are Rainwater Tritium T-01, R1 located in the Rainwater Sr-89, -90 Sr-01, R0 SQN Radiological { Rainwater Gross Beta G-01, R1 SQN Laboratory Soil Gross Beta G-01, R1 SQN Procedures I Surface Water Gross Alpha G-01, R1 SQN Manual Surface Water Gross Beta G-01, R1 SQN Ground Water Gros,s Beta G-01, R1 SQN Sediment Gross Alpha G-01, R1 SQN Sediment Gross Beta G-01, R1 SQN Class Gross Alpha G-01, R1 SQN Clams Cross Beta G-01, R1 SQN Fish Gross Alpha G-01, R1 SQN Fish Gross Beta G-01, R1 SQN Fish Sr-89, -90 Sr-01, R0 SQN Vegetation Sr-89, -90 Sr-01, R0 Vegetation I-131 1-03, R0 BFN Fruit Gross Pata G-01, R1 Vegetables Gross Beta G-01, R1 Meat / Poultry Gamma G-03, R1 q Meat / Poultry Gross Beta G-01, R1 Atmospheric Tritium T-01, R1 SQN Moisture I 1 m i

~ Regulatory Guide 4.15 Recommended Procedures i Abbreviations: RLPM Radiological Laboratory Procedures Manual ERMM Environmental Radiological Monitoring Manual FONRE Fld Ops NRE Procedures Manual FOIM Fld Ops Instrumentation Manual FOBRPM Pld Ops Biological Resources Procedures Manual RDPM Radiation Dosimetry Procedures Manual l Function Manual Procedure Sample collection ERMM Chapt'er 1, R3 ENVR-3, R4 ^ RLPM SC-01, R0 FONRE S&P OPS-FO-NRE-41.1, R2 S&F OPS-FO-NRE-41.2, R2 S&P OPS-FO-NRE-41.3, R2 FOBRPM NR OPS-FO-BR-21.6, R0 NR OPS-FO-BR-21.ll, RO NR OPS-FO-BR-23.1, RO NR OPS-FO-BR-23.3, RO NR OPS-FO-BR-23.9, R0 Sample packaging, RLPM SC-01, RO shipment, & receipt FONRE S&P OPS-FO-NRE-41.1, R2 S&F OPS-FO-NRE-41.2, R2 S&F OPS-FO-NRE-41.3, R2 FOBRPM NR OPS-FO-BR-22.1, RO I Sample preparation RLPM SP-01, RO i FOBRPM NR OPS-FO-BR-22.7 R0 NR OPS-FO-BR-22.8, R0 1 i Laboratory standards: RLPM STD-01, R1 maintenance, storage, STD-02, R1 & use STD-03, R0 STD-04, R1 STD-05, R0 i I l l 4 4

s 1 Regulatory Guide 4.15 (con't) Recommended Procedures ) Abbreviations: RLPM Radiological Laboratory Procedures Manual ERMM Environmental Radiological Monitoring Manual FONRE Fld Ops NRE Procedures Manual j FOIM Pld Ops Instrumentation Manual l FOBRPM Fld Ops Biological Resources Procedures Manual j RDPM Radiation Dosimetry Procedures Manual i Function Manual Procedure Equipment calibration RLPM OP-O1, R1 & routine operation OP-02, R0 OP-03, R0 OP-05, R1 1 OP-06, RO OP-08, R1 QASTD-0006, RO QC-01, RO QC-02, RO QC-03, RO QC-04, R2 QC-05, no QC-07, RO QC-08, R0 ) QC-09, R0 i QC-10, R1 i QC-ll, RO j QC-12, RO j QC-13, R1 QC-14, RO i j QC-16,~ R0 j QC-18, RO i QC-20. R0 QC-21, RO j QC-25, R1 QC-100, R0 RDPM ENVIR, R2 FOIM NR OPS-FO-NRE-62.1, RO !i I NR OPS-FO-NRE-62.2, R0 I, NR OPS-FO-NRE-62.3, R0 NR OPS-FO-NRE-62.4, R0 NR OPS-FO-NRE-64.41, R0 i 1' Data reduction, ERMM Chapter 2, R3 evaluation, & Chapter 4, R3 } reporting ENVR-4, R4 1 I ~ l i 1 l l i

Regulatory Guide 4.15 (con't) Recommended Procedures Abbreviations: RLPM Radiological Laboratory Procedures Manual _ L*. ERMM Environmental Radiological Monitoring Manual FONRE Fld Ops NRE Procedures Manual ~ POIM Fld Ops Instrumentation Manual FOBRPM F1d Ops Biological Resources Procedures Manual RDPM Radiation Dosimetry Procedures Manual Function Manual Procedure Meteorlogical NR OPS-FO-NRE-61.1, RO equipment calibration ~ NR OPS-FO-NRE-61.2, RO NR OPS-FO-NRE-61.3, R0 NR OPS-FO-NRE-61.4, R0 NR OPS-FO-NRE-61.5, RO NR OPS-FO-NRE-61.6, R0 NR OPS-FO-NRE-61.ll, R0 NR OPS-FO-NRE-61.12, R0 NR OPS-FO-NRE-61.13 R0 NR OPS-FO-NRE-61.14 RO l

s SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL (ODCM) Change 1 ~ ~ DESCRIPTION OF CHANGE: Sections 3.3 and 3.4 added. ANALYSIS OR EVALUATION JUSTIFYING CHANGE: These sections are added to define the requirements for an interlaboratory comparison program and a land'use survey.' They are added to the ODCM to document these requirements which appear in the Technical Specifications. This will ensure that all Technical Specification requirements appear in the ODCM. EVALUATION OF ACCURACY OF DOSE CALCULATION OR SETPOINT DETERMINATION This change reflects no change to the dose calculation or setpoint determination methodology,'and therefore, no evaluation of accuracy is 4 necessary. Change 2 DESCRIPTION OF CHANGE: c Table 3.1-1, Section 1.a., under Sampling and Collection Frequency, the phrase is added "(more frequently if~ required by dust loading)". ANALYSIS OR EVALUATION JUSTIFYING CIULNGE: i j This change is made to the ODCM to document requirements which appear in the Technical Specifications. This will ensure that all Technical Specification requirements appear in the ODCM. EVALUATION OF ACCURACY OF DOSE CALCULATION OR SETPOINT DETERMINATION: This change reflects no change to the dose calculation or setpoint f j determination methodology, and therefore, no evaluation of accuracy is necessary. .J

l l Change 3 1 j DESCRIPTION OF CHANGE: } Table 3.1-1, Section 1.a., under Type and Frequency of Analysis, the first s ':. _ two sentences are changed to read, " Analyze for gross beta radioactivity 24 hours following filter change. Perform gamma isotopic analysis on each ~~ j sample if gross beta 10 times the yearly mean of control sample." ANALYSIS OR EVALUATION JUSTIFYING CHANGE: This change is made to the ODCM to document requirements which appear in the Technical Specifications. This will ensure that all Tech Spec requirements appear in the ODCM. EVALUATION OF ACCURACY OF DOS'E CALCULATION OR SETPOINT DETERMINATION: 1 This change reflects no change to the dose calculation or setpoint determination methodology, and therefore, no evaluation of accuracy is necessary. l Change 4 } DESCRIPTION OF CHANGE: TaDie 3.1-1, Section, 4.a., under Type and Frequency of Analysis, the requirement now reads " Gamma isotopic and I-131 analysis of each sample. SR-89, 90 once.per quarter." ANALYSIS OR EVALUATION JUSTIFYING CHANGE: l This change is made to the ODCM to document requirements which appear in the Technical Specifications. This will ensure that all Technical Specification i requirements appear in the ODCM. EVALUATION OF ACCURACY OF DOSE CALCULATION OR SETPOINT DETERMINATION: This change reflects no change to the dose calculation or setpoint l methodology, and therefore no evaluation of accuracy is necessary, i i Change 5 1 DESCRIPTION OF CHANGE: j Table 3.1-1, Section 4.a., under Sample Locations change "If samples are not 4 available from an area" to "If samples are not available from a milk animal j location." 1 i

ANALYSIS OR EVLAUATION JUSTIFYING CHANGE: This change is made to clarify at which locations the vegetatioh'su.mples are to be collected. These samples are to be obtained at those locetior.s designated as milk t.nimal 1ccations when a milk sample is not available. J: _ EVALUATIONOFACCURACYOFDOSEChtCULATIONORSETFOINTDETERMINATION: ~ ~ ' This change reflects no change to the dose calculation or setpoint determination methodology, and therefore, no evaluation of accuracy is i necessary. Change 6 DESCRIPTION OF CHANGE: Table 3.1-1, Section 4, add a section c. Invertebrates (Asiatic clams). Sample Locations: TRM 496.5 TRM 483.4 TRM 480.8 Sampling and Collection Freqdency: At least once'per 184 days. Type and Frequency of Analysis; Gamma scan on edible portion. ANALYSIS OR EVALUATION JUSTIFYING CHANGE: This change is made to the ODCM t'o document requirements which appear in the Technical Specifications. This will ensure that all Technical Specifications requirements appear in the ODCM. EVALUATION OF ACCURACY OF DOGE CALCULATION.OR SETPOINT DETERMINATION: This change reflects no change to the dose calculation or setpoint I cetermination methodology, and therefore, no evaluation of accuracy is ne cessary. Change 7 f DESCRIPTION OF CHANGE': Table 3.1-1, Section 4.c., changed to Section 4.d. Last sentence under Sample Locations is deleted. ANALYSIS OR EVALUATION JUSTIFYING CHANGit: This change is rtade to make the ODCM more compatible with the Technical Specifications. The requirement for changing _ sampling locations based on the land use survey is too time constraining to be accomplished. g i I e E M,,

EVALUATION OF ACCURACY OF DOSE CALCULATION OR SETPOINT DETEMRINATION: This change reflects no change to the dose calculation or setpoint determination methodology, and therefore, no evaluation of accuracy is necessary. -J. Change 8 ~~' DESCRIPTION OF CHANGE: Table 3.1-1, Section 4.d. changed to 4.e., under Sample Locations, first sentence changed to read "one sample from up to three locations." ANALYSIS OR EVALUATION JUSTIFYING CHANGE: This change is a clarificatio'n of the requirement. EVALUATION OF ACCURACY OF DOSE CALCULATION OR SETPOINT DETERMINATION: This change reflects no change to the dose calculation of setpoint determination methodology, and therefore, no evaluation of accuracy is necessary. Change 9 DESCRIPTION OF CHANGE: Table 3.1-2 and 3.1-3, reference numbers are added for each sample station and each water supply respectively. ANALYSIS OR EVALUATION JUSTIFYING CHANGE: These reference numbers are added to provide a cross-reference between the Tables and the Figures which appear in the ODCM. EVALUATION OF ACCURACY OF DOSE CALCULATION OR SETPOINT DETERMINATION: This change reflects no change to the dose calculation or setpoint determination methodology, and therefore, no evaluation of accuracy is necessary. Change 10 DESCRIPTION OF CHANCE: Table 3.2-1 is replaced. ANALYSIS OR EVALAUTION JUSTIFYING CHANGE: j This change is made to the ODCM to document requirements which app, ear in the Technical Specifications. This will ensure that all Technical Specification requirements appear in the ODCM.

i i EVALUATION OF ACCURACY OF DOSE CALCULATION OR SETPOINT DETERMINATION: This change reflects no change to the dose calculation or setpoint determination methodology, and therefore, no evaluation of accuracy is necessary. =a ,_=_o Change 11 DESCRIPTION OF CHANGE: Figures 3.1-1, 3.1-2, 3.1-3, 3.1-4, 3.1-5, 3.11-6, and 3.1-7 are replaced. ANALYSIS OR EVALUATION JUSTIFYING CHANGE: These figures are replaced wi,th figures showing the locations indicated by the reference numbers to be used in the tables. This will allow an easier cross reference between the tables and figures. EVALUATION OF ACCURACY OF DOSE CALCULATION OR SETPOINT DETERMINATION: This change reflects no change to the dose calculation or setpoint determination methodlogy, and therefore, no evaluation of accuracy is necessary. Change 12 DESCRIPTION OF CHANGE: Figures 3.1-6 and 3.1-7 have one milk sampling location deleted. ANALYSIS OR EVALUATION JUSTIFYING CHANGE: These milk sampling locations have been deleted due to one dairy going out of business and the relocation of several goats to a location outside the 5-mile range. EVALUATION OF ACCURACY OF DOSE CALCULATION OR SETPOINT DETERMINATION: This change reflects no change to the dose calculation or setpoint determination methodology, and therefore, no evaluation of accuracy is necessary. Change 13 DESCRIPTION OF CHANGE: SQN ODCM pages 11, 13, 14, and 16 and RAP 1.2 sections 4.0 and 5.3 have been changed to reduce the action level (by a factor of 2) for which Step 2 is used to calculate monthly gaseous doses. Further, RAP 5.3 has also been revised to include an action level for which the Air Quality Branch will be requested to provide actual monthly meteorological data to Radiological Health for use in the monthly gaseous dose calculations.

ANALYSIS OR EVALUATION JUSTIFYING CHANGE: A review of SQN monthly versus quarterly doses for 1984 indicated that the monthly methodology was less conservative than the quarterly methodology for three quarters out of the year. This condition was due to the fact that the ~ _: e actual quarterly Chi /Qs were larger (by up to 68 percent) than the historical Chi /Qs used for the monthly calculations. To compensate for this apparent lack of conservatism in the monthly methodology, the action level -7 for performing the Step 2 methodology (specified in the ODCM) was reduced by a factor of 2. Further, an action level has been introduced into the RAP 1.2 for which AQB will be requested to provide Radiological Health with actual monthly meteorological data. EVALUATION OF ACCURACY OF DOSE CALCULATION OR SETPOINT' DETERMINATION: This change will not affect s'etpoint determinations. This change will help ensure that the monthly methodology is at least as conservative as the quarterly methodology in estimating gaseous pathway doses. l =

This section of the ODCM describes the methodology that will be used to perform these monthly calculations. Doses will first be calculated by a simplified conservative approach, J (step 1). If these exceed the specification limits, a more realistic ' calculation will be performed (step 2). f.2.1 Noble Cases Step 1 Doses will be calculated using the methodology described in this step. If +ny-limits are exceeded, step 2 will be performed. 4 So piuod 4 h appAG hh Equations and assumptions for calculating doses from releases of, noble follows: gases are as Assumptions 1. Doses to be calculated are gamma and beta air doses. 2. The highest annual-average X/Q based on licensing meteorology for ground level releases for any offsite location will be used. 3. No credit is taken for radioactive decay. 4. For gamma doses, releases of Xe-131m, Xe-133, Xe-135, Ar-41, and ' Kr-88 are considered. k 5. For beta doses, releases of Xc-131m, Xe-133, Xe-135, Kr-85, and Ar-41 are considered. 3 6. Dose factors are calculat ed using dat a from TVA's nuclide library. 7. The calculations extrapolate doses assuming that only 90 percent of total dose was contributed. 8. A semi-infinite cloud model is used. 9. Building wake effects on effluent dispersion are considered. Equations For determining the gamma dose to air: g' Dy = _(X/Q) 108 Q. DFy. (1.12) j 15 0.9 3.15 x 10' 1 1 i ~ q mL i Revision 5

Page $ Step 2 D This methodology is to be used if the calculations in Step 1 yield r-doses that exceed applicable limits. .g9 n. Equations and assumptions for calculating doses to air from releases J of noble gases are as follows: Assumptions 1. Doses to be calculated are gamma and beta air doses. 2. Dose is to be evaluated at the nearest site boundary point in each sector. 3. Historical onsite meteorological data from the period 1972-1975 will be used. 9 4. All measured radionuclide releases are considered. 5. A semi-infinite cloud model is used. 6. Radioactive decay is considered. l 7. Buildi,ng wake effects on effluent dispersion are considered. 8. Dose f actors are calculated using data from TVA's radionuclide libra Equations s, Equations for calculating air concentration, X, is the same as in Section 1.1.1, step 1, part A. the site boundary in each sector. Air concentrations are calculated for For determining the gamma dose to air D, = t, X,1 DFy (1.16) g 5 i where: D = gamma dose to air for sector n, mrad. X,1 = air concentration of radionuclide i in sector n, pCi/m 3 DFyi = gamma-to-air dose factor for radionuclide i, mrad /yr per 1 pCi/m3 (Table 1.5). t, = time period considered, yr 4 Revision 9. -. - - - - _.

Page S For determining the beta dose to air: Dp = t, ni DFpg (1.17) x n .i where: DE = beta dose to air for sector n, mrad. ~ n X"1. = air concentration of radionuclide i in sector n, pCi/m3 DFE g = beta to air dose factor for radionuclide i, mrad /yr per g pCi/m3

• 1 1'

t, = time period considered, yr !Thesectorhavingthehighest total dose is then used to check compliance with specification 3.11.2.2. 1.2.2 Iodines and Particulates i Step 1 Doses will be calculated using the methodology described in this step. If any limits are exceeded, step 2 wi11 be performed. Equations and assumptions for calculating doses from releases of iodines and particulates are as follows: Assumptions 1. Doses are to be calculated for the infant thyroid from milk ingestion and for the child bone and teen g. i. tract from i vegetable ingestion. 2. Real cow locations are considered for the milk pathway and nearest resident-locations with home-use gardens are considered for the g vegetable pathway. g 3. The highest annual-average D/Q based on 1972 to 1975 meteorological l doses. data for ground level releases will be used for ingestion pathway 6l 7 4.' No credit is taken for radioactive decay. 5. Releases of I-131 are considered for the milk pathway. 4 Sr-90 releases are considered for the vegetable pathway to the child bone. I Co-58 releases are considered for the vegetable pathway to the teen 7 g.i. tract. 6. The calculations extrapolate doses assuming that only 9D percent of the total dose was contributed. 7. The cow is assumed to graze on pasture grass for the whole year. " Revision 7

r Step 2 This methodology is to be used if th alculations_in step 1 yield doses that exceedgpplicable limits ~- ~ QPuttri %/ ~ ~ Doses for releases of iodines and particulTttes slii ~ 6 calc lated using the methodology in Section 1.1.1, step 1, part B, with the t following exceptions: 1. All measured radionuclide releases will be used. 2. Dose will be evaluated at real cow locations and will consider actual grazing information. The receptor having the highest total dose is then used to check compliance with specification 3.11.2.3. Calendar quarter doses are first estimated by summing the doses calculated for each month in that quarter. Calendar year doses are first estimated by summing the doses calculated for each month in that year. He ever, if the annual doses determined in this manner exceed or approach the specification limits, doses calculated for previous quarters sith the methodology of section 1.4 will be used instead of the doses estimated by summing monthly results. 8 1.3 Dose Projections I In accordance with specification 3.11.2.4, dose projections will be ( performed ( This will be done by averaging the calculated dose for ( the most recent month and the calculated dose for the previous month and assigning that average dose as the projection for the current month. 1.4 Quarterly and Annual Dose Calculations A complete dose analysis utilizing the total estimated gaseous releases for each calendar quarter will be performed and reported as required in Specifications 6.9.1.8 and 6.9.1.9. Methodology for this analysis is the same as that described in Section 1.1.1, except that real pathways and receptor locations (Table 1.4) are considered. In 9 addition, meteorological data representative of a ground level release for each corresponding calendar quarter will be used. This analysis will replace the estimates in Section 1.2. At the end of the year an annual dose analysis will be performed by calculating the sum of the quarterly doses to the critical receptors. 1.5 Gaseous Radwaste Treatment System Operation The gaseous radwaste treatment system (GRTS) described below shall be maintained and operated to keep releases ALARA. 1.5.1

System Description

A flow diagram for the GRTS is given in Figure 1.3. The system consists of two waste gas compressor packages, nine gas decay tanks, and the associated piping, valves, and instrumentation. Gaseous Revision 9.

Page 6 I Sgtd onc 370 Radiological Environmental Monitoring 1.,,I 3.1 Monitoring Program An environmental radiological monitoring p'rogram shall be conducted ~ in accordance with Technical Specification 3.12.1. The monitoring -~ program described in Tables 3.1-1, 3.1-2, and 3.1-3, and in Figures 3.1-1, 3.1-2, 3.1-3, 3.1-4, 3.1-5, and 3.1-6 shall be conducted. l 12 Results of this program shall be reported in accordance with Technical Specifications 6.9.1.6 and 6.9.1.7. The atmospheric environmental radiological monitoring program shall consist of 11 monitoring stations from which samples of air 12 particulates and atmospheric radiciodine shall be collected. The terrestrial monitoring program shall consist. of the collection of i milk, soil, ground water, drinking water, and food crops. In-addition, direct gamma radiation levels will be measured in the vicinity of the plant.. The reservoir sampling program shall consist. of the collection of samples of surface water, sediment, and fish. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, sample unavailability, or to malfunction of sampling equipment. If the latter, every effort shall be made to complete corrective action prior ( to the end of the next sampling period. 3.2 Detection Capabilities Analytical techniques shall be such that the detection capabilities listed in Table 3.2-1 are achieved.

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' g. SQN L TABLE 3.1-1 RADI0 LOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sampling and Type and Frequency and/or Sample Sample Locations

• Collection Frequency of Analysis 1.

AIRBORNE A u :,1 < fu s p r er 1 s I. c /c. r a L'c. a;. //s

• 4Y

'?l'/Av4/f !:sf.% 's.9 A'lVceehu;e. a. Particulates 4 samples frosi locations Continuous sampler -Gross-beta--a t -least once (in different sectors) at operation with sample -per'-Wddy[, gamma,c"' j,',f,,, or near the site boundary collection once per isotopic analysis #1f (LM 2, 3, 4 atd 5) 7 days Coore (', r/a u.J/j gross beta:10 times n a'n Ye a,,y r .'[ r *"# u s'ie' / /r,.' cl u s f. of control sample. r / ^ ,' #1 / - Composite at least once s, per 92 days (by location for gamma scan. 4 samples fron communities approximately 6-10 miles distance from the plant (PM 2, 3, 8, and 9) 3 samples fron control locations greater than 10 miles from the plant (RM 1, 3, and 4) 5N b. Radioiodine Samples from same locations Continuous sampler 131 on n 1 at least once per mg as Local (LM) and Remote (RM) operation with filter 7 days N{ air particulates collection once per 7 days g n

• Sample locations are shown on Figures 3.1-1, 3.1-2, 3.1-3, 3.1-4, 3.1-5, and 3.'l-6.
  • Samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours (Sheet 1 o'f 5) j

(, Revision 12 I a

• I l

's ~^ l .xy r TABLE 3.1-1 (continued) l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sampling and Type and Frequency and/or Sample Sample Locations

• Collection Frequency of Analysis c.

Soil Sample; from same locations Once per 3 years Gamma scan, 37 80,90 as air particulates once each 3 years 2. DIRECT RADIATION 2 or more dosimeters placed Once per 92 days Gamma dose at least at 10 of the air particulate once per 92 days sampling stations (LM-3, LM-4, LM-5, PM-2, PM-3, PM-8, PM-9, RM-1, RM-3, and RM-4) ( 2 or more dosimeters placed j at each of at least 30 other locations. (Figures 3.1-2 and 3.1-5) 3. WATERBORNE a. Surface TRM 497.0 Collected by automatic Gamma scan of each (Figure 3.1-4) TRM 483.4 sequential-type sampler ** composite sample. TRM 473.2 with composite samples Composite for tritium collected over a period analysis at least of 5 31 days once per 92 days b. Ground 1 sample adjacent to At least once per 92 Gross beta, gamma scan 8N (Figure 3.1-2)' plant (location W-6) days and tritium analysis 5{ at l~ east once per 92 ou g days g n I sample from ground vi water source upgradient (Sheet 2 of 5) Revision 12 'O o

--s . t i:).. 'elen t TABLE 3.1-1 (continued) RADIOLOGICAL ENVIRONMENTAL MONITORING FROGRAM Exposure Pathway Sampling and Type and Frequency and/or Sample Sample Locations

• Collection Frequency of Analysis c.

Drinking 1 sample at the first Collected by automatic Gross beta and gamma scan (Table 3.1-3) potable surface water sequential-type sampler ** of each composite sample. (Figure 3.1-4) supply downstream from with composite sample Comgositefortritium, the plant (TRM 473.0) collected over a period so. oSr at least once of 5 31 days per 92 days 1 sample at the next 2 Grab sample once per 31 downstream potable surface days water suppliers (greater than 10 miles downstream) (TRM 470.5 and 466.3) 2 samples at control locations Samples collected by automatic m> (TRM 497.0 and TRM 503.8) sequential-type sampler with $N composite sample collected over a period of 5 31 days d. Sediment TRM 496.3 At least once per Gamma scan of each sample TRM 483.4 184 days TRM 480.(8 Trit 472.6 c. Shoreline TRM 485 At least once per 184 Gamma scan of each sample Sediment TRM 478 days (Figure 3.1-4) 'TRM 477 4. INGESTION L,,y. % /c p,'c AJ " *k a,q,g.3 j-. wf, g '. sample from milk producing At least once per 15 days Mil'k 1 a. W -analysis' semi-I (Figure 3.1-6) animals in each of 1-3 areas , monthly.on collection. indicated by the cow census. -Gamma-scan at least. where doses are calculated .once.per.31-days to be highest. If samples 89e90Sr C Jf CU # # r" l M V [ C T. d (Sheet 3 of 5) Resision412 'e a

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D 1: j.. L',. TABLE 3.1-1 (continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l Exposure Pathway Samplin'g and Type and Frequency and/or Sample Sample Locations

• Collection Frequency of Analysis m;/!: % /.

are not available from.an ,once per quarter tosa//'3rea, doses to that area will s j be estimated by projecting U [h l the doses from concentrations J detected in milk from other l sectors or by sampling vegetation where milk is not available (Table 3.1-1, 4.d) l At least I sample from a control location. b. Fish I sample each from Nickajack, At least once per 184 Gamma scan on edible l Chickamauga, and Watts Bar days. One sample of portion Reservoirs each of the following species : Channel Cattish C-

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-ri.h !! ^(0. r White Crappie ,t et g 3',N Smallmouth Buf falo (.,.c -~**;

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qp f-g, j,,, -; ,, 7 ; ;.,: g G.1, a.,.; :; w., Gh .I d. Food Products I sample each of principal At least once per 365 Gamma scan on edible food products grown at days at time of portion l private gardens and/or harvest. The types yR farms in the immediate of foods available gg vicinity of the plant. for sampling will vary. n . Selection-of-locations to Following is a list of o( .be based on the-land use typical foods which may n . census. be available: vi l i l (Sheet 4 of 5) Revision 12 i 9 ' b f f' l ? !g 2

(n, y N i TABLE 3.1-1 (continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sampling.and Type and Frequency _and/or Sample Sample Locations

• Collection Frequency of Analysis Cabbage and/or Lettuce Corn Green Beans Potatoes Tomatoes cep b 4, e d. Vegetation 1 sample f rom each-of-At least once per 31 Gamma scan at least (Figure 3.1-6) three locations of milk-days once per 31 days.

l producing animals where 89Sr and 90Sr a'nalysis l a sample of milk is not at least once per 92 I available and at each air days particulate station i i i m> un EE i n l U{ s

sn tn (Sheet 5 of 5) 4 c

Revisi6n1'2 ' i ' !0 .e

t l-g Page 12 'g s g-SQN ~ l' TABLE 3.1-2 l ATMOSPIIERIC AND TERRESTRIAL -:= ? MONITORING STATION LOC ~, S ~= 9#f. ao-5 < HY ,y y [ h S .1 LM-2 SQ Location LM-3 SQ Approximate Distance and 3, Direction from Plant t/. LM-4 SQ f' LM-5 SQ 0.8 mile N 7 l.3 mile SSW PM-3 SQ (Daisy)PM-2 SQ (Chester Frost P 1.5 miles NE f ark) 7 PM-8 SQ (Harrison) l.7 miles NNE f* PM-9 SQ (Lakeside) 3.8 miles SW 5.6 miles W /.'_. 'RM-1 SQ (Chattanooga, Riverside) 8,7 miles SSW d RM-3 (Cleveland) f RM-4 (Dunlap) 2.7 miles WSW At /(, Farm L 16.7 miles SW /7 Farm M 11.3 miles ESE i tP Farm J 19.5 miles WNW !? Farm IN Farm EM 2.8 miles-NNE zo As Farm BR 3.5 miles NNE 't Farm LE 1.3 miles W ') Farm GO 1.3 miles NW W Farm SU 2.5 miles N M Farm C (control) 2.3 miles SSW JG Farm B (control) 3.5 miles S A7 Farm S (control) 1.7 miles E 3.3 miles SSE 16.0 miles NE 43.0 miles NE 12.0 miles NNE ? Revision 12 i ~ .m

Page 13 SNP .3

1. d TABLE 3.1-3

_1 e s , C PUBLIC WATER SUPPLIES SAMPLED IN ENVIRONMENTAL MONITORING PROGRAM N # I p C a_ I b4V - Distance Sampling /f37 ~- Water Supply from Site Source Frequency' Il Chattanooga (C. F. Industries) 11.5 Tennessee River Monthly * (mile 473.0) 0_ Chattanooga (E. I. DuPont and 14.0 Tennessee River Monthly Company) (mile 470.5) Jp Chattanooga 19.0 Tennessee River Monthly (mile 465.3) 3 b 12.5 Tennessee River Monthly (mile 497.0) };f' Dayton 19.3 Tennessee River Monthly" (mile 503.8) a. Sample collected by an automatic sequential-type water sampler with (' composite sample taken monthly. b. Sample collected at 473.0 is taken from raw water supply; therefore, the upstream surface water sample at 497.0 will be considered a control sample for drinking water. Revision 12

• ..~

Page 14 -(Sheet 1 of 4) \\ TABLE 3.2-1 T.M \\ DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS d- ._o a A. ' Specific Analyses 5 NOMINAL LOWEH LIMIT OF DETECTION (LLD) Air Vegetation i Particulates Charcoal Fallout Water and grain 3 3 2 pCi/m pCi/m mci /km pCi/l pCi/g, dry Gross a 0.005 0.05 2.0 0.05 Gross p 0.01 2.3 0.20 3H 330 333I 0.01 89Sr 0.005 10 0.25 90Sr 0.001 2 0.05 Fish Soil and clam flesh, Foods, meat, Sediment

plankton, Clam shells poultry Milk pCi/g, d ry pCi/g, dry pCi/g, dry pCi/kg, wet pCi/l Gross a 0.35 0.1 0.7 i

Gross 0.70 0.1 0.7 25 (' 3H 231I 0.5 89Sr 1.5 0.5 5.0 40 10 SO Sr 0.3 0.1 - 1. 0 8 2 i j i l in j

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Attachm:nt 5 Page 15 (Sheet 2 of 4) TABLE 3.2-1 (Continued) IN \\ DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS \\ b ~ \\ B. Camma Analyses - - s .y ~ NOMINAL LOWER LIMIT OF DETECTION (LLD) ~ g Air kater Vegetation Soil and particulates and milk and grain sediment. Fish 3 pCi/m pCi/l pCi/g, dry pCi/g, dry pCi/g, dry 141 144Ce 144 Ce 0.02 s 33 0.22 0.06 0.06 stCr 0.03 \\ 44 0.47 '0.10 0.10 831 1 0.01 \\ 8 0.09 0.02 0.02 103:10sRu \\ Ru 0.03 \\

4_0, 0.51 0.11 0.11

• 0G 234 Cs 0.02 y '."

0.33 0.08' O.08 137Cs 0.01 5 0.06 0.02 0.02 95Zr-Nb i 85Zr 0.01 10 0.11 0.03 0.03 SSNb 0.01 5 0.05 0.01 0.01 i 58Co 0.01 5 0.05 0.01 0.01 54 Mn 0.01 5 0.05 0.01 0.01 85Zn - 0.01 9 0.11 0.02 0.02 60Co 0.01 5 O.06 0.01 0.01 j 40g j [ 140Ba-La I 340 Ba 0.02 25 0.34 0.07 0.07 240La 0.01 7 0.08 0.02 0.02 f, g', f... ld

0. 9 Clam Flesh Foods, tomatoes Heat and and plankton Clam shells potatoes, etc.

poultry pCi/g, dry pCi/g, dry pCi/kgm, wet pCi/kgm, wet 141 144 Ce 344 Ce 0.35 0.06 52Cr 0.56 0.10 33 40 181I 0.07 0.02 44 90 9 103 10sRu 8 20 losRu 0.74 0.11 i 334Cs 0.48 0.08 40 90 137 Cs 0.08 0.02 26 50 85Zr-Nb 5 15 85Zr O.15 0.03 95Nb 0.07 0.01 10 20 ssCo 0.07 0.01 5 15 54 Mn 0.08 0.01 5 15 65Zn 0.17 0.02 5 15 60Co 0.08 0.01 9 20-4OK 5 15 240Ba-La 340Ba 0.30 0.07 25 50 340La 0.10 0.02 7 15 l Revision 12

Pagt 16 (Shret 3 ef 4) f.u S. TABLE 3.2-1 (Continued) .p TABLE NOTATIONS ~ ~ - - x-a. All LLD values for isotopic separations are calculated by the method develope'd by Pasternak and Harley as described in RASL-i 300. Factors such as sample size, decay times, chemical yield, and counting efficiency may vary for a given sample; these variations may change the LLD value for the given sample. The assumption is made that all samples are analyzed within one week of the collection date. / / The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical sepa ra tion): 4.66 s g_ b E V 2.22 y exp(-A A t) ~ where f-LLD is the lower limit of detection as defined above (as pCi per f. unit mass or volume) s is the standard deviation of'the background counting rate or b et the counting rate of a blank sample as appropriate (as counts per minute) E is the counting efficiency (as counts per transformation) V is the sample size (in units of mass or volume) 2.22 is the number of transformation per minute per picoeurie Y is the fractional radiochemical yield (when applicable) A is the radioactive decay constant for the particular radionuclide t is the elapsed time between sample collection (or end of the sample collection period) and time of counting The value of s used in the calculation of the LLD for a detection b system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. Revision 12

Attachmtnt 5 Page 17 (Sheet 4 of 4) s TABLE 3.2-1 (continued) ^~ g cw e:) TABLE NOTATIONS ' ~ b. The Ge(Li) LLD values are calculated by the methods developed.by Pasternak and Harley as described in IIASL-300. These LLD values are expected to vary depending on the activities of the components in the samples. These figures do not represent the..LLD values achievable on given samples. Water is counted in either a 0.5-L or 3.5-L Marinelli beaker. Solid samples such'as soil, sediment, vegetation and clam shells are counted in a 0.5-L Marinelli beaker as dry weight., The average dry weight is 400-500 grams (125g for vegetation). Air filters and very small volume samples are counted in petrie dishes centered in the detector endcap. The counting system consists of a ND-6620 multichannel analyzer and a germanium detector having an efficiency of at least 20 percent. The counting time is normally 4-8 hours. All spectral analysis is performed using the sof tware provided with the ND-6620 or the computer program HYPERMET. The assumption is made that all samples are analyzed within one week of the collection date. The LLD values listed in this table may change slightly after c. routine evaluation of background, sample size, counting times, etc.. The most recently calculated values will be included in the Annual Ra'diological Environmental Operating Report. g Revision 12-

f r ( l/ 3 )- (S4eal 3, 2 - l TABLE -4d e--l-MAXIMUM VALUES FOR Tile LOWER LIMITS OF DETECTION (LLD)a,c j g 1 l Airborne Particulate Water or Ga3 Fish Milk Food Products Sediment c (pCi/1) (pCi/m ) (pCi/kg, wet) (pCi/1) (pCi/kg, wet) (pCi/kg, dry) Analysis z -2 gross beta 4 1 X 10 N.A. N.A. N.A. N.A. H-3 2000 N.A. N.A. N.A. N.A. N.A. Mn-54 15 N.A. 130 N.A. N.A. N.A. Fe-59 30 N.A. 260 N.A. N.A. N.A. Co-58,60 15 N.A. 130 N.A. N.A. N.A. d 5 Zn-65 30 N.A. 260 N.A. N.A. N.A. 3, Zr-95 30 N.A. N.A. N.A N.A. N.A. l Nb-95 15 N.A. N.A. N.A. N.A. N.A. b -2 I-131 l 7 X 10 N.. A. 1 60 N.A. -2 Cs-134 15 5 X 10 130 15 60 150 g, kk -2 Cs-137 18 6 X 10 150 18 80 180 tj Ba-140 60 N.A. N.A. 60 N.A. N.A. 2R [I EE '\\ M i ^ La-140 15 N.A. N.A. 15 N.A. N.A. I oo s E. a g 7l., l 'l 'I. b* e e

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\\ e! 3,' ~ 5le,5f : a 7,,,_ _ i Page 19 TABLE.4.-12-1 (Continued) TABLE NOTATION ' ', -- c ~~ The LLD is the smallest concentration of radioactive material in a .7 a. sample that will be detected with 95% probability with 5% probability _f of falsely concluding that a blank observation represents a ".real" signal. For a particular measurement system (which may include radiochemical separation): 4.66'sb LLD = E exp(-Aat) Y 2.22 V Where: LLO is the "a priori" lower limit of detection as defined above (as picccurie per unit mass or volume), is the standard deviation of the background counting rate or s Do. the counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per transformation), V is the sample size (in units of mass or volume), 2.22 is the number of transformation per minute per picocurie, Y is the fractional radiochemical yield (when applicable), A is the radioactive decay constant for the particular radionuclide, and at is the elapsed time between sample collection (or end of the sample collection period) and time of counting (for environmental samples, not plant effluent samples). The value of s used in the calculation of the LLD for a detection systemshallbNbasedontheactualobservedvarianceofthebackground counting rate or of the counting rate'of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples). Typical values of E, V, Y and at shall be used in the calculations. c5EQUDYAH2=UNITT -3/4-12-8 ~ 0Asias13 j u

's h, ~ ':.ia+f ~. Attrchment 5 e Page 20 7, 2-- ! 1.":) - TABLE.4.12-1 (Continued) TABLE NOTATION ~~._e b. The LLD for analysis of drinking water and surface water samples ~~ shall be performed by gamma spectroscopy at approximately 15 pCi/A. If levels greater than 15 pCi/1 are identified in surface water samples downstream from the plant, or in the event of an uncntici-pated release of I-131, drinking water samples will be analyzed at a LLD of 1.0 pCi/A for I-131. Other peaks which are measurable and identifiable, together with the c. radionuclides in Table 4.12-1, shall be identified and reported. f e j \\'.. -$EQUOYAtt---UNIT--2 s -3/4-12e9' Nevb*oy 13

Page 21 Figure 3.1-1 h)- ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK e ATMOSPHERIC AND TERRESTRIAL SAMPLES COLLECTED AT EACH STAT!ON _,7 g RADIOLOGICAL MONITORING STATIONS DAY ON DUNLAP J ./ S ALE CR EK R:k4 - DY 8 EORGETOWN ( - f D:-2 LM-5-sp-I 7 PM-3-SQ%I SQN P%9[,$ J.. SQ $: 2 -Sq- /v A D g SIGP L RED BAN MOUN TAIN b3_.SQ. W G P 98-SQ-4' CHICK A M GA DAM i MILES 4 en li E CHATTANOO A LOOKOUT w. IS MILES MOUNTAIN 20 MIL ES REV 12 O

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r o '. Figure 3.1-4 Page 24 R ES ER VOIR MONITORING NETWORK SEQUOYAM NUCLE AR PL ANT a _ ; DAYTON (MIL E 503. 0,0AYTON) j$ l .7 d MILE 497 MIL E 4 9 6.S SODDir( DAISY S E QUOYAH MILE 485 NUCLEAR PLANT I MIL E 4 8 3.4 MILE 400B MILE 478 y CHICKAMAUGA MILE 477 ? ~. DAM (MILE 470.5, E.1. DUPONT) (M7LE 4710. C. F. INDUSTRIES) MIL E 4 73.2 MILE 4 7 2.8 I 3Y (M:LE 65.3, CHATTANOOGA) SHOREUNE SEDIMENT l f-* 4 /

• _ AUTOMATIC WATER SAMPLER Y' ' *

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S.,.y f 4.- 0 } @ Milk and vegetation collected - r= w mn.-u.. _.., " +-r e - Miles [- e Vegetation only co]Iected ~ Note: Vegetation is also collected each air arlnitoring station. at See Figure 3:l'-1. ~ U 12 ~ 1 j

( C. b' Page 27 l'i gu rs 'i. ] -7 p'.,. - rlll.A SAMI'l.ING l.Of;ATIONS e c%

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l I h6 THIS PAGE INTENTIONALLY LEFT B M e f i

p .T r s TENNESSEE VALLEY AUTHORITY ' Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 March 12, 1986 Nuclear Regulatory Commission Office of Management Information and-Program Control Washington, DC 20555 Gentlemen: SEQUOYAH NUCLEAR PLANT - MONTHLY OPERATING REPORT - FEBRUARY 1986 Enclosed is the February 1936 Monthly Operating Report to NRC for Sequoyah Nuclear Plant. Very truly yours, TENNESSEE VALLEY AUTHORITY 3 4- ^ " P. R. Wallace Plant Manager Enclosure cc (Enclosure): Director, Region II Nuclear Regulatory Commission Office of Inspection and Enforcement Suite 3100 101 Marietta Street Atlanta, CA 30323 (1 copy) Director, Office of Inspection and Enforcement Nuclear Regulatory Commission Washington, DC 20555 (12 copies) Mr. A. Rubio, Director Electric Power Research Institute P. O. Box 10412 Palo Alto, CA 94304 (l' copy) INPO Records Center Suite 1500 '100 circle 75 Parkway Atlanta, GA 30339 (1 copy) Mr. K. M. Jenison, Resident NRC Inspector. j O&PS-2, Sequoyah Nuclear Plant j 1983-TVA SOTH ANNIVERSARY An Equal Opportunity Employer -.}}