ML20214L553
| ML20214L553 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/30/1986 |
| From: | Dupree D, Wallace P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8609100259 | |
| Download: ML20214L553 (76) | |
Text
4 4
4 TABLE OF CONTENTS f
I.
Operational Summary Page 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 2-3 Offsite Dose Calculation Manual Changes 4
II. Operating Statistics o.
A. ' NRC Reports Unit One Statistics 5-7 Unit Two Statistics 8-10 B.
TVA Reports Nuclear Plant Operating Statistics 11 Unit Outage and Availability 12-13 Reactor Histograms 14 III. Maintenance Summary Electrical Maintenance 15-16 Instrument Maintenance 17-25 Mechanical Maintenance 26-29 Modifications 30-37 IV.
Environmental Qualification (EQ) Summary 38-44 4
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PERFORMANCE
SUMMARY
June 1986 The following summary describes the significant operational activities for the month of June. In support of this summary, a chronological 1
log of significant events is included in this report.
I The units remained in an administrative shutdown the entire month due to design control review, configurattan' control updating and resolution of sigcificant employee concerns. Outage related maintenance and modifications are being performed.
Unit I has been off-line 312 days.
Unit 2 has been off-line 313 days.
SIGNIFICANT OPERATIONAL EVENTS Unit 1 Date Time Event e
06/01/86 0001C The reactor was in mode 5.
The administrative shutdown due to design control review, config-uration control updating and resolution of significant employee concerns continues.
06/30/86 2400C The reactor was in mode 5.
The administrative shutdown due to design control review, config-uration control updating and resolution of significant employee concerns continues.
Unit 2 Date Time Event 06/01/86 0001C The reactor was in mode 5.
The administrative shutdown due to design control review, config-uration control updating and resolution of significant employee concerns continues.
06/30/86 2400C The reactor was in mode 5.
The administrative shutdown due to design control review, config-uration control updating and resolution of significant employee concerns continues.
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n FUEL PERFORMANCE Unit 1 The core average fuel exposure accumulated during June was O MWD /MTU with the total accumulated core average fuel exposure of 0 MWD /MTU.
Unit 2
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The core average fuel exposure accumniated during June was 0 MWD /MTU with the total accumulated core average fuel exposure of 8097.51 MWD /MTU.
SPENT FUEL PIT STORAGE CAPABILITIES l
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.
Pres,ently, 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 June 1986.
LICENSEE EVENT REPORT (S) i The following licensee event reports (LERs) were reported to the Nuclear Regulatory Commission in June 1986.
LER Description of Event 1-86022 Two containment ventilation isolations (CVIs) occurred May 15, 1986 at 0140 CST (Unit 1) and at 0356 CST (Unit 2) respectively. The first event was caused by electromagnetic interference generated by relay vibration on the radiation monitor 1-RM-90-131 while placing containment purge in operation.
The second event occurred on_ unit 2 while performing maintenance and trying to prevent a similar event as described above from transpiring.
It was decided to remove power from radiation monitor 2-RM-90-106 to avoid a CVI.
Personnel were unaware that the power loss would initiate the system to the safe position and actuate a CVI.
A design change request will be initiated to modify the
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radiation monitoring system and special instructions will be issued for future reference.
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o LICENSEE EVENT REPORT (S)
(continued)
LER Description of Event
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1-86023 The Technical Review Committee discovered that the radio-active liquid effluent monitoring instrumentation channel calibration had not been performed per surveillance requirement (SR) 4.3.2.9.C.S.a, which is required once every 18 months. A procedure for the calibration of a flow indicator on the condensate demineralizer line was never instituted. However, a rotometer cannot be calibrated and if found inaccurate must be discarded.
A channel check was performed to verify operability as required.
" Calibration of Compliance Instruments",
(SI-198), will ensure in the future that the TVA test facilities will verify the accuracy of all rotometers that will be installed.
1-86024 On May 25, 1986, the hourly firewatch required by technical specification 3.7.12 was not fully completed between the hours of 1300 and 1400 CDT.
2-86002 A containment ventilation isolation (CVI) occurred due to a cognitive personnel error while performing Surveillance Instruction (SI)-166.29 " Control Air Check Test During Cold Shutdown". This was the result of a low flow condition to the upper containment radiation monitor (2-RM-90-112) when the monitor's containment isolation valves were allowed to drift partially closed during the test. Arching of the low flow switch initiated a spike causing a high radiation signal. During the writing of the test procedure there was failure to anticipate the potential of a CVI.
A revision to the procedure will be submitted to advise personnel that such potential effects exist during performance of this test.
2-86003 Two CVIs occurred due to spurious spikes on radiation monito rs. RM-90-106B spiked due to a loose wire on the flow switch. RM-90-112 spiked due to welding noise (EMI).
SPECIAL REPORT (S)
The following special report was submitted to the NRC in June 1986.
Report #
Description 66-06 On June 17, 1986, at 1414 CST, all of the plant fire pumps were removed from service for 37 minutes.
The pumps were removed from service to allow for the replacement of three hypochlorite valves (0-VLV-50-552, 523, and 521) that are located on one-inch lines close to the pumps. The replacement of the subject valves was due to excessive Icakage. These valves are used to chlorinate the fire protection system in the control of Asiatic clams.
SPECIAL REPORT (S) (continued)
Report #
Description 86-06 The fire detection system was operable during the entire activity.
Upon detection of a fire, the pumps could have been started manually and the fire suppressiou s~ystem~ pressurized. Before removing the.
pumps-from service, communications were established between the main control room and the work area in accordance with plant procedures.
The maintenance activity complied with technical specifications and plant procedures.
Physical Security Instruction 13, " FIRE," was followed during the_ event.
OFFSITE DOSE CALCULATION MANUAL CHANGES Offiste dose calculation manual changes were finalized April 14, 1986. A copy of the changes is found in section V.
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t OPERATIONAL SUmfARY O
m O
e OPERATING STATISTICS (NRC REPORTS)
O l
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OPERATING DATn MEPORT DOCKET NO. $0-327
{
DATE JULY 3,1986 COMPLETED DY D.C.CUPREE TELEPHONE (615)G70-6544 OFERATING STATUS 1.
UNIT NAME: SEGUOYAH NUCLEAR PLANT, UNIT 1
NOTES:
~
2.
REPORT PERIOD: JUNE 19S6 3.
LICENSED THERMAL POWER (MWT):
3411.0 4.
N/NEPLATE RATING (GROSS 11WE):
1220.6 5.
DESIGN ELECTRICAL RATING (fJET MWE):
1148.0 6.
MAXIMUM DEPENDABLE C AP ACITY (GROSS MWE):
1183.0 7.
MAXIMUM DEPENDABLE CAPACITY (NET MWE):
1148.0 8.
IF CHANGES OCCUR IN CAPACITY RATINGS (ITEl1S NUM3ERS 2 - THROUGH 7)SINCE LAST REPORT, GIVE REASONS:
9.
EI4ER LEVEL TO WHICH RESTRI'CTED.IF ANY(NET MWE):
~
- 10. EEASONS FOR RESTRICTIONS, IF ANY:
THIS MONTH YR.-TO-DATE CUMULATIVE
- 11. HCURS IN REPORTING PERIOD 720.00 4343.00 43324.00
- 12. N:.MDER OF HOURS REACTOR WAS CRITICAL O.00 0.00 24444.91
- 12. 7EACTOR PEFERVE SHUTDOWN HCURS 0.00 0.00 0.00
- 14. HOURS GENEPATOR ON-LINE O.00 0.00 20371.13
- 15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
- 16. GFOSS THERMAL ENERGY GENERATED ( f1WH) 0.00 0.00 77060971.91
- 17. GPOSS ELECTRICAL ENERGY GEN. (MWH) 0.00 0.00 25976386.00
- 18. MET ELECTRICAL ENERGY GENERATED (!1WH )
-3045.00
-203G1.OO 24922356.00
- 19. UNIT SERVICE FACTOR O.00 0.00 54.47
- 20. UNIT AVAILABILITY FACTOR O.00 0.00 54.47
- 21. UNIT CAPACITY FACTOR (USIf>G (1DC NET) 0.00 0.00 49.54
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 49.54
- 23. UNIT FORCED OUTAGE RATE 100.00 100.00 29.85
- 24. *UTDOWN3 SCHEDULED OVCR NGXT 6 idONTHS (iYPE, DATE, AND CURATiCN OF EACH):
25.
F SHUTDOWN AT END OF REPOR T PERIOD, ESTI 1ATED DATE OF STARTUP:
S TAR TUP IS UNDETEmilNED AT THIS TIfiG PENDING DESIGN CONTROL REVIEW, CCNFIGURATION CONTROL UPDA1ING, AND RESOLUTION OF SIGNIFICANT EMPLOYEE CONCERNS.
NOTI MAT THE THE,YR.-TO-CATE AND CUMULATIVE VALUES HAVE UEEN UPDATED..
SEOUOYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL DOCKET NO. : 50-327 UNIT : DNE DATE : JULY 3,1986 COMPLETED BY :
D. C. DUPREE TELEPHONE :CB153870-6544 MONTH: JUNE 1986 AVENAGE, DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe Net)
DAY (MWe Net) 01 0
1G O
02 0
17' O
03 0
18 0
04 0
19 0
05 0
20 0
06 0
21 0
4 07 0
22 0
08 0
23 0
09 0
24 0
10 0
25 0
l 11 0
26 0
12 0
27 0
13 0
20 0
14 0
29 0
15 O
30 0
f
UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-327 UNIT NAME Sequoyah One I
DATE July 5, 1986 COMPLETED BY D.
- c. Dupree REPORT MONTH JUNE 1986 TELEPHONE (615)870-6544 f
n se o
C gg; o yg Licensee g <r, gvb Cause & Corrective Ny
- y y ;j g Event g]
gy Action to No.
Date o
o y
g 5g*
Report #
go gu Prevent Recurrence co 5"
$55 1
7 851220 F
720 F
9 Design Control, Configruation Updating, andEmployeeConcerns.l i
7 i
2 3
4 8F:
Forced Reason:
Method:
Exhibit G-Instructions 2
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-Afministrative 5-Reduction SExhibit I-Same Source G-Operational Error (Explain) 9-Other Il-Other (Explain)
,4'
CPERAT!NG DATA' REPORT DOCKET NO. 50-328 DATE JULY 3,1996 COMPLETED BY D.C.DUPREE 1
TELEPHONE (615)S70-6544 OPERATING STATUS 1.
UNIT NAME: SEOUOYAH NUCLEAR PLANT, UNIT 2
NOTES; 2.
REPORT PERIOD: JUNE 1986
- 3.. LICENSED THERMAL POWER (MNT):
3411.0 4.J NAMEPLATE RATING (GROSS MWE):
1220.6 5.. DESIGN ELECTRICAL RATING (NET MUE):
1148.O 6.
MAXIMUM DEPENDADLE CAPACITY (GROSS MWE):
1183.0 7.. MAXIMUM DEPENDADLE CAPACITY (NET MWE):
1148.0
-8.
IF' CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS O THROUGH 7)SINCE LAST REPORT, GIVE REASONS:
9.
PCWER' LEVEL TO WHICH RESTRICTED. IF ANY(NET MWE):
- 10. EEASONS F R RESTRICTIONS, IF ANY:
d THIS MONTH YR.-TO-DATE CUrlVLATIVE -
- 11. HOURS IN REPORTING PERIOD 720.00 4343.00 357G4.00
- 12. NLM3ER OF HOURS REACTOR WAS CRITICAL O.00 0.00 21984.54
- 13. REACTOR RESERVE SHUTCOWN HOURS 0.00 0.00 0.00
- 14.. HCURS GENERATOR ON-LINE O.00 0.00 21494.42
- 15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
- 16. GFOSS THERMAL ENERGY GENERATED (MWH) 0.00 0.00 69127977.22
- 17. GFOSS ELECTRICAL ENERGY GEN. (MWH) 0.00 0.00 233367S0.00
- 18. NET ELECTRICAL ENERGY GENERATED (MWH)
~5586.00
-29770.00 22603187.60 j.
- 19. UNIT SERVICE FACTOR O.00 0.00 60.07
- 20. UNIT AVAILABILITY FACTOR O.00 0.00 60.~07
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 55.02
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 55.02 l
- 23. UNIT FORCED OUTAGE RATE 100.00 100.00 30.43 j
- 25. UF SHUTDOWN AT END OF REPOk'I I'ERICD,
~
~
ESTIMATED DATE OF STARTUP:
TFE RESTART OF UNIT-2 HAS 3EEN SCHECULED FOR JANUARY 1987.
NOTE illAT THE THE YR.-TO-DATE AND
' CUMW ATIVE VALUES HAVE BEEN UPDATED.
2,
1 SEQUOYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL DOCKET NO. : 50-328 UNIT : TWO DATE : JULY ~3,1986 COMPLETED BY :
D. C. DUPREE TELEPHONE :(6153870-6544 MONTH: JUNE 1986 AVEEAGE. DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY Ct1We Net)
DAY Ct1We Net) 01 0
16 O
O2 0
17 0
03 0
18 O
04 0
19 0
05 0
20 0
06 0
21 0
07 0
22 0
08 0
23 0
09 0
24 0
10 0
25 0
11 0
26 0
l 12 0
27 0
13 0
28 0
14 0
29 0
l 15 0
30 0
i i
i
UNIT SifUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-328 UNIT NAME Sequoyah Two DATE July 5, 1986 COMPLETED BY D. C.
Dupree REPORT MONTH JUNE 1986 TELEPHONE gl5)S70-6544 E
o cg oeg Licensee g s, g
Cause & Corrective Ny No.
Date g
gg ytg Event gg gg Action to o
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5gM Report #
gu gu Prevent Recurrence 5"
?G5 R
7 850821 F
720 F
4 Design Control, Configuration Updating, and Employee Concerns.
3F:
Forced 2Reason:
3Method:
4Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-ttanual for Preparation of Data B-!!aintenance or Test 2-!!anual Scram.
Entry Sheets for Licensec 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.!ministrative 5-Reduction G-Operational Error (Explain) 9-Other SExhibit I-Same Source II-Other (Explain)
. i!
OPERATING STATISTICS (TVA REPORTS) l l
1 1
L s
TVA 6560C (PP 3 76)
UNIT OUTAGE AND AVAILA8tuTY Sequoyah Nuclear Plant Licensed Reactor Poner 3411 MW(th)
Unit No._
ho Generator Rating 1220.5 MW(e)
Design Gross Electrical Rating 1183 Month / Year _ June 1986 MW Perio<f flours 720 T.<ne ua :A a. sable Tome hot Awastable METif0D OF UNIT Tiene Tun.
T ctal Gen Not thed Turbine Gen.
Reactor Umt Out in CORRECTIVE ACTION OUTAGE CAUSE S
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SEQc3YAH ONE REACTOR HISTOGRAM 110
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SU? DIARY OF MAINTENANCE ACTIVITIES S
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SUMMARY
07-14-86 PAGE 1 COMP D.00dP U FUNC STS ADDRESS. D ATE.... CESCRIPTI0N............................. CCRRECTIVE ACTI0N.......................
B103193 1 GENB 032 0001B 01/31/86 1-GENB-082-0001B-Br[tNPRD*3,1PB D/G 1-GENB-82-1B-B IDLE SPEED SETTING WAS PARELY PASSES SI 7 TS 3.8.1.2 CRITERIA SET TOO LOW TO MEET TEST CRITERIA.
OF REACHING 60HZt0R-1.2 IN 10 SEC.LAST ADJUSTED PNEUMATIC P00 STER AND IDLE
)
TEST TOOK 9.9 SEC. INVESTIGATE 1 IMFROVE SPEED SETTING FER THE VENDOR INSTR ALSO I
START TIME TO PREVENT FUTURE FAILURES OF ADJUSTED MINIMUM-MAX EXCITATION CURRENT SURVEILLANCE TESTS LEVEL POINT FER VENDORS MANUAL MR B105193 B10M02 1 ZS C33 0071 2 02/11/06 1-2S-063-0071 1-2S-63-71 2-A LIMIT SWITCH MOUNTING 2-A,ItNFRD*,*10CFR50.49t], CLOSED LIGHT FRACKET WAS PENT FREVENTING LIMITS FROM SOCKET WILL NOT GIVE INDICATION OF MAKING UP. STRAIGHTENED LIMIT SWITCH CLOSED POSITION SUSFECT FROBLEM WITH MOUNTING BRACKET AND CHECKED FOR FROFER
'.IGHT SOCLET LIGHT INDICATION. MR B105202 B103470 1 GENB 082 0001A 01/31/86 1-GENB-082-0001A-A,[tNFRDt], INVESTIGATE 1-GENB-82-1A-A EXCITATION CCNTROL TIME VOLT. 1 FREQ NOT WITHIN TECH SPEC LIMITS DELAY TRIP CURRENT LEVEL WAS OUT OF DURING INITIAL START F/ AMBIENT ADJUSTMENT. ADJUSTED THE MINIMUM-MAX CONDITIONS >10 SECS PERIODICALLY EXCITATION CONTROL TIME CELAY TRIP CURRENT LEVEL TO MINIM SET POINT FER VALIDATED INSTRUCTION MANUAL MR B105470 B103492 2 FCTA 202 CJ /2 01/22/86 2-BCTA-202-CJ /2,CtNFRDt],C0!L BURNED 2-BCTA-202-CJ/2 TRIP COIL HAD EURNED IN PKR WOULD NOT TRIP FREVENTING IREAKER FROM TRIFFING.
REPLACED TRIP COIL AND CHECKED FOR PROFER OPERATION. WR B105492 B111744 1 GENB 082 0001A 02/05/86 1-GENB-082-0001A-A,HS-82-165 CONTACT 0-HS-82-165-A ROTARY SWITCH WAS PAD DUE APPEAR TO MAKE UP INTERMITTANTL.
TO AGE OR CYCLIC FATIGUE. REPLACED ROTARY SWTICH AND CHECKED FOR PROPER OFERATION MR B111744 B111745 2 GENB 082 0002A 02/05/86 2-GENB-082-0002A-A, HAND SWITCH 82-195 0-HS-82-225-A ROTARY SWITCH WAS BAD DUE CONTACTS AFFEAR TO MAKE UP TO AGE AND CYCLIC FATIGUE. REPLACED INTERMITTANTLY ROTARY SWITCH AND CHECKED FOR PROPER CFERATION MR B11745 B113221 2 CENB 082 0002B 02/18/86 2-GENB-082-0002B-Be[*NPRD*],ENG 1 2-GENB-82-2B-B IMERSION HEATER IMMERSION HTR CONTACTOR CONTACTS ARE CONTACTOR CONT ACTS WERE PURNED AND BURNED AND PITTED. DG 721 FITTED DUE TO AGE. REPLACED CONTACTS IN HEATER CONTROLLER CONTACTER. MR B113221 B113222 2 GENB 082 00%B 02/18/86 2-GENP-082-0002B-Be[*NPRD*],ENG 2 2-GENB-82-2B-B IMERSION HEATER IMMERSION HTR CONTACT 00 CONTACTS ARE CONTACTOR CONT ACTS WERE PURNED AND PURNED AND FITTED. DG EL 721 PITTED DUE TO AGE, OR NORMAL WEAR.
REFLACED CCNTACTS IN HEATER CONTROLLER CONTACTCR MR B113222 P115938 1 HS 030 0451C 06/09/86 1-HS-030-0451C-A,WHEN YOU G3 TO START CONTACT IN SUITCH WAS PROKEN.
FCSITION WITH HS IT WILL NOT START FAN DISASSEMBLED AND REFLACED ROTOR CAM WHEN YOU GO TO STOP POSITION WITH HS IT B115938 WILL NOT STOP FAN INVEST AND REFAIR AS NEEDED B118255 1 XS 063 0334C 05/27/86 1-/S-058-0324C-B,HANDSW PLACK GRIP IS FOSSIBLY, S2 ITCH HANDLE BROKE FROM WEAR.
EROKEN. REFLACE HS REPLACED SWITCH HANDLE UR B118255 B121183 0 MTRB 078 0020 05/:8/86 OMTFB-078-0020,ItNFRDt), REPAIR R'#P PUMP MOTOR 'B' WAS FAD. REF WR B117263
ELECTRICAL KAINTEN ECE GONTHL7 SUMGARY 07-0?-S6 F20E 2 COMP
'R. COMP U FUNC SYS ADDRESS. PATE...
0ESCRfPf!0N............................. CORRECTIVE ACT109..................
MTR B VITH PARTS FROM RWFP MTR A FEF WR FOR U0F.K ON Ft'MP. PEMOVED B121176 AND ROTOR AND FEPLACCD WITH TFE EH.FT
~
FROM 0-MTRB-78-19 AND CFECKED FOR FECFER OPERATION. UR B121163
! recoeds listed.
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r MAINTENANCE sum!ARY (INSTRUMENTATION)
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INSTRUMENT MAINTENANCE MONTHLY REPORT FOR JUNE 1986 UNIT 1 During performance of SI-102, fuel oil pressure indicators, PI-18-68/2 and PI-18-83/2, were determined to be inoperable because of clogged snubbers (PRO 1-86-131). The snubbers were replaced and the instruments were returned to service.
UNIT 2 PRO-2-86-044 was initiated when EMI from steam generator U-tube welding caused a containment vent isolation signal to be generated from radiation monitor loop 2-R-90-112.
During channel calibration testing of steam generator level loop L-3-93, LT-3-93 was found outside the desired tolerance. An evaluation of all loop component "as found" values revealed that the technical specifications allowable value for LS-3-93-B was not satisfied.
PRO-2-86-045 was initiated and the loop was'recalibrated.
During performance of SI-484, instrument mechanics discovered a partial loss of fill fluid in the train A upper plenum sense line for the Reactor Vessel Level Instrumentation System. Work is currently underway to determine cause and necessary corrective action.
Prepared special maintenance instruction SMI-2-90-1 to perform noble gas calibration for the shield building postaccident radiation monitors.
COMMON Completed Instrument Maintenance Section's responsibilities for replacement of parts on the units 1 and 2 hydrogen analyzers to maintain environmental qualification.
Initiated PRO-1-86-145 to evaluate possible problems with the main feedwater control valves not meeting the required technical specification response times for feedwater isolation.
Completed review of preliminary setpoint methodology report.
Coordination with Westinghouse to resolve comments and correct problem areas is currently underway.
Completed Workplan 12056 to correct drawing discrepancies (as described in Discrepancy Report No. SQ-DR-86-03-082R) with time delay relay settings for control room isolation signal.
Initiated program to verify the technical adequacy of all surveillance instructions required by technical specifications. The problem involves a technical review, revision, and reperformance (as required) of each instruction, and is scheduled for completion before startup.
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..... CORRECTIVE ACTION........
Al-li FART IV ATI T
't24242 2 P1 060 311C 06/17/86 2-PT-Ol8-311C,PE26 02M A f! ELD DCTAIN NEW CATA AND UPDATE EGIS FOT UERIflCATIDW SD THE TRAN!dlTIER PER HPRDS REPORTABLE.kE B124140 Al-19 PART IV ATT 7 0125300 2 EE 090 100 Ce/27/86 2-WE-090-100,lDDIP.E FL3W ALARM PICKED IUDlHE FLDW SulTCH DUT Uf fALICGATIUrt.
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LOW BACKCROUND. SETPUINT TGu HIGIL S1204 LOWERED SETPOINT 0125737 0 RM 090 140A C6/27/86 0-Pn-090-140A, YELLOW LICHT IS IN SI LOW EACFCDUND. SETPDINT TUG HICH.
204 LDUERED 1ETPu!NT 0130619 0 03: WeRIC'J S 06/1?/86 0--032-VARIGOS, CHECK FDR AND REPnIR LDDSE FITTINGS TIGHTEHED FITTINGS kR lea:S IN SEN!32 LlHE COHR UP TU AND D130619 IRSIDE PWL 0 L 321 0131167 0 PCU 026 15 04/13/86 0-PCV-026-15, PRESSURE WAS 180 PSI Al DEFECTIVE POSITIDHER. REPAIRE0 DISCHAREE Dr LUMPS WITH 1AA AhD 100 flRE PDSITICHER WR C131167 PJMPS RUHHING SUSPECT PCU 26-15 HDT fuhCTIDNING PRDPERLY INUES AND FEPAIR C131176 2 R.1 07) 106 G6/06/86 2-Rh-090-106-0, CHECK RRD nGN FDR CAUSE LD3SE ELECTRICAL C0KHECT!Da Od IQDIRE Dr SPIFE THAT RESULTED IN CONT UENT ISDL FLDR SklJCH TICHTEHED LUUfE CCed.CCTIch P.EEDED TO AdSHER PRO 2 86 043 WR B131176 D131182 2 FI 072 34 06/26/86 2-fi-072-34,00NT SPEAY PUMP 2A-A FLOW FLOW TFAN$nlTTER SENSING LINES HEEDED INDILATDR SH0HING APPRDX 1000 GPM FLCW DACKf!LLINC. BACKf!LLED SENSING LihES B1313a8 0 FR 090 103 06/24/86 0-RR-090-103, BLUE PEN ON RECORDER IS LUDSE CDNNECTION ON RECliRDER. TIGHTENED NOT n00lHC WHEN hDNiidk IS SOURCE C6HWECTION WR B131358 CHECKED 0131363 2 RM 090 112 06/17/U6 2-Rh-090-112, PULL CUI RELAYS FOR 2 RN HDHE REINSTALLED WR D131363 9J 112 A AND D REINSTL WHEN WR 122280 IS COMPLETE B131382 0 Rn 090 122 06/20/86 0-R.1-090-122,NDN LOW FLOW ALARN STICKS DIRTY SWITCH. CLEAdiD Su!TCH MR C131382 DCCASICHAILY C131963 2 flC 04.
57 C6/18/86 2-FIC-046-5?, CONTROLLER DDESN'T SWITCH-CONTROLLER 00T Of CALIBRATION M90ES AUTU AND HANUAL WNEN SWITCHED IN RECALICRATED NR D131963 CONTRdl RDun B132258 1 FIC 013 0057 06/03/86 1-flC-046-0057-S,DDTAIN HAnE PLATE DATA UNKNOWN. UPDATE EGIS.
FUN THE ALDi:VC LISTED DEUICE B132261 1 LIC 003 UARIC"5 06/03/661-IIC-003-VARJUUS,Di:RAlk NAME PLATE UNKNDNN. UPDATE EGIS. NOT iifRDS DalA FLR 1LIC-3-140 156 164 171 172 173 'REPORTA0LE. ee
IHSTRU.1EHT n;iafEhi.niE cEdfHLY SUNP.A27 07-03-06 PAGE 4 C0fiP MR.CDnP U FUNC SYI 700EE!S. DATE... CESCRIPIIDH.
.. CORRECTIVE ACTION..
174 175 0132551 2 PT 001 U 06/06/86 2-Pi-001-5-G,UERifY MDUHTING PER UHkHOWH TORGUED CULTS HDI HFROS SMI-0-317-26 REPURTABLE WR C132351 C132306 1 PT 001 30 06/06/86 1-PT-001-30-G,UERifY MOUNTING PER UHKHUWN TOWGUED CULT NOT HPRDS SMI-0-317-26 REPDETABLE WR C132358 C132361 1 TT 000
- 35) C6/06/86 1-fi-003-354-D,UERIf7 MOUNT!HG FER UNENDWH TOCQUED CULTS HOT HPRDS SnI-0-317-26 REPDRfABLE kR 8132361-B132362 1 TT 003 35D 06/06/86 1-fi-003-35B-E, VERITY n0VHTING PER UHRHOWN TORQUED E0tTS NOT kFPOS Sn!-0-317-26 REPORTABLE WR B132362 B132343 1 fl U33 40n 06/06/86 1-fl-0C3-486-D,UERIFY n00HITING PER UNKHDuH TORQUE COLT NOT HFRDS Sn!-0-317-26 REPORTA0LE WR B132363 0132364 1 fr 001 400 05/06/U6 1-fi-003-4SD-E,UER!fY NDUNTING PER UHKNDWN TORQUED COLTS HDf HPf5S SnI-0-317-26 REPURTABLE WR 8132364 0132365 1 ff 00?
9Ch 06/06/86 1-ff-003-90A -D,UERIfY n0UNT!hG PER UHkHOWN TURQUE BJLTS HQI HPROS Sn!-0-317-26 REPORTABLE WR B132365 0132366 1 FT 00s 901: Cf/06/06 1-fi-003-90D-E,UERIfY MDUHTING PER UNKH04H TORQUED COLIS HDI BPRS3 Sd!-0-317-26 WEPORTADLE WR B132366 D132367 1 FI 00i 103a 06/66/861-fi-003-103A-D,UERifY n00HT!HG PER UhkHOWH TURQUE BOLTS WR B132347 Sn!-0-317-26 HDT HPROS REPORIABLE B132532 1 FT 07:-
0013 06/26/86 1-fT-072-0013-D.PIS CALIBRATE FLOW ROHE. UER!f!ED CALIBRAT10H RETORHED TO IHDICATOR 1-fi-72-13 FCR PERf 0RnANCE Of SERVICE. HDT kPRDS REPORTABLE kR 0132532 SI-37 B132751 2 PT 001 iA 06/02/C6 2-PT-001-96-D,UERiff n0UHT!HG PER UNKRDWH.. TORGUED BOLTS. n3T HPPDS Snl-C-317-26.
REPORTA0LE.
B132752 2 PT 00 90 C6/02/86 2-PT-001-90-E,UERITY DDUHTIN0 PER UHWHDhH. TORQUE BULTS. HDT HPFES Sdi-0-317-26 REPORTaDLE B132753 2 PT 601 12 06/06/86 2-PT-001-12-I,UERIFY MOUHilkG PER UHRH0dH TORQUED CULTS HDT.1PPDS 3d1-0-317-26 REPDRTADLE WR B132753 0132754 2 PT 001 203 ot/02/86 2-Pi-001-20A-D,UERifY MOUNTING PER UNRHOWN. TORQUED ESLT. HDT HPAD3 Snt-0-316-26 REPORTADLE.
C132755 2 FI C01 200 06/02/86 2-Fi-001-200-E,UERIfY MOUNTING PER UHkHOWN. TORQUED 00LTS. NOT hPR&S Snt-0-317-26 REPORIABLE B132756 2 PI U01 23 66/06/06 2-P'l-001-23,UERITY THE HOUHTINGf PER UHKHOWN 10RG0ED BOLTS HOT MfRDS Shl-0-317-26 REPORTABLE WR B132756 0132737 2 PT 001 30 06/06/86 2-PT-001-30-G, VERIFY hDUHlING PER UHKHDWH TORGUED BDLTS HDT kPRD Sni-0-317-26 REPDRTALLE WR B132757 B132758 2 PT 001 72 06/06/86 2-PT-001-12-E UERifY n00HIING PER UNKNOWN TORGUED CULTS HOT hPRDS Sn!-C-317-26 REPORTABLE WR B132758 B132759 2 Pi 001 73 06/U6/86 2-Pi-001-73-D,UERiff n00HTING ffR UNKHDWH 10R00ED BOLTS HOI hfRDS SMI-0-317-26 REPORTABLE WR B132759 0132769 2 Pl 030 30C 06/06/66 2-PT-030-300,UERIFY hDUHTING PER UNKNOWN TURQUED BOLTS WR C132769..!'
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MAINTENANCE SUlefARY (MECHANICAL)
O f5
MECHANICAL MAINTENANCE MONTHLY REPORT FOR JUNE 1986 COMMON
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1.
Continued work on ERCW pump "RA" to replace the upper pump shaft which had become too rough to allow the shaft. sleeve 0-Ring to seal.
a A special maintenance instruction was prepared for this work which is currently on hold pending receipt of a new shaf t sleeve.
.j i
2.
The shaft sleeve and packing were replaced on "PB" ERCW pump.
3.
Finalized our maintenance instruction enhancement plan utilizing assistance from four Westinghouse engineers under a personal services contract.
4.
The Plant Operating Review Committee approved a maintenance instruction revision adding the maintenance instruction writers guide as well as issuing seventeen new maintenance instructions.
Provide'd fire door training to responsible carpenters, foreman, planners, 5.
engineers, engineering aides, and engineering section supervisor on the new fire door, channel calibration of safety inspection system accumu-lation water level revision, and Physical Security Instruction-13
(" Fire") requirements.
6.
Completed rebuilding the "B" turbine building sump pump.
7.
Performed a preventive teardown, repair, and reassembly of miscellaneous Crane Chem pumps to prolong their life.
8.
Began investigation for a generic FCR on stress corrosion cracking of B6 bolting in POSI-SEAL Butterfly Valves due to a problem found on an ERCW pump discharge valve.
9.
Completed the replacement of the seats on CO2 Pilot valves at the diesel generator building.
10.
Replaced a head gasket on "BB" auxiliary control air compressor.
11.
Completed the annual inspection of IBB diesel generator.
12.
Provided carpenter support for various walkdowns including unit one snubber nameplate data collection.
13.
Replaced a failed rupture disc on "A" boric acid evaporator package.
14.
Removed sixteen red rubber gaskets'from miscellaneous locations inside containment for degradation evaluation.
15.
Seals in the auxiliary building crane gear boxes were replaced.
16.
Participated in this radiological emergency plan drill.
17.
Completed Surveillance Instruction (SI-149) on damper inspections.
/
MECHANICAL MAINTENANCE MONTHLY REPORT FOR JUNE 1986 UNIT 1 1.
Completed replacement of the boric acid system valves and piping which exhibited signs of stress corrosion cracking.
2.
Replaced wire rope on the polar crane small hook.
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HEC ANICAL MAINTENANCE MONTHLY REPORT FOR JUNE 1986 UNIT 2 1
1.
Began inspecting and repairing the long cycle valves (2-FCV-3-191, 192,193,194 and 2-VLV-3-568) due to leak through problems.
2.
Reassembled the 2A component cooling water pump af ter replacing the shaft sleeves.
3.
Continued repairing the failed containment isolation valves.
4.
Complet'ed workplan 11948 stelliting the after terry-turbine steam trap internals due to erosion problems.
5.
Reinforced the damaged insulation on the reactor head.
6.
Completed post sludge-lancing inspections and closed up the steam generators.
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MAINTENANCE SU?&fARY (MODIFICATIONS) l 1
I l
I
SUMMARY
OF WORK COMPLETED MODIFICATIONS JUNE 1986 NUREG 0588 ECN 6231 - Remove Interferences The removal of one support and the addition of three supports were completed; however, additional work is anticipated (see ECN 6681).
ECN 6552 - 0588 Solenoids Functional testing was performed on one valve because of other work in progress on this valve by Maintenance.
ECN 6616 - Damper Fusible Link Workplan preparation was completed, and it was placed in the approval cycle.
APPENDIX R ECNs 5435, 6343, and 6344 - Fire Doors The replacement and repair of the doors and doorframes (ECNs 6343 and 6344) were completed. The installation of weatherstripping continues as resources permit.
ECN 6235 - Reroute Various Cables This work is complete.
ECN 6311 - Operator Extension on PORV This work has been completed except for final cycling at startup.
ECN 6315 - Replace Fuses This work is complete.
ECN 6319 - Fire Protection Piping
-m This work is complete.
ECN 6642 - Annulus Fire Protection and Sealing Containment Penetrations This work is complete.
C,
OTHER ITEMS 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 The workplan for the replacement of isolation valves remains in the approval cycle.
Some insulation activities remain incomplete. DNE is revising the USQD.
Based upon DNE's analysis, some additional hanger work may be required for the piping replaced on the upper compartment cooler lines inside containment.
ECNs 5034, 5713, 5743, and 6064 - Various Platforms in Lower Containment The first trolley was modified by the vendor and found acceptable.
The remaining trollies are being prepared for shipment to the vendor for modification. Work will continue when the trollies are returned.
ECN 5202 - Interface of Fifth Diesel With Other Diesels This work is no longer scheduled for this time period.
ECN 5620 - Add Instrumentation for Auxiliary Feedwater Pump Work is on hold and is not scheduled for this time period.
ECN 5657 - Installation of MSR Drain Valves Reinsulation romains incomplete. Caps have been installed on the valve nipples.
ECNs 5703 - Reinforcement of Block Walls During the installation of the restraints, some mortar joints were broken.
Efforts are underway to repair these joints before the restraints are installed.
ECN 5724 - CVCS/RHR Supports i
Three hangers and two notifications of indication remain incomplete.
1 ECN 5914 - Improve Reliability of Steam Dump i
This wor'k is ccmplete. -
ECNs 5938, 6305, and 6571 - Replace Feedwater Heater and Eroded Pipe
~
Mechanical Modifications is supporting postmodification testing (PMT) on both units as requested.
Insulaticn work on unit 1 contin'tes.
Installation of the monorail on unit 2 continues.
ECN 6057 - Cable Tray Covers Approximately 240 out of 290 cable tray covers have been romanufactured or replaced.
ECN 6147 - Airlock Packing Nut Final testing of the airlocks on unit 2 remains incompleto.
ECM 6185
,0ffsite Paging System Because additional versatility is needed, new EPROMs and crystals were ordered.
Further work will be required.
ECN 6196 - Pressurizer Hangers and Valves PMT is incomplete and scheduled for startup.
ECN 6204 - Electrical Penetration Overcurrent Protection Fuse replacement and fuse block installation are complete.
Electrical Modifications is awaiting a procedure change to place the circuits in service.
ECN 6259 - Moisture Separator Reheater Tube Bundle Replacement Insulation activities are continuing. The decision was made to replace the unit 2 bundles, and work was begun. The moisture separator reheaters were stripped, and three high-pressure bundles were removed. Work is continuing.
.c ECN 6380 - Replacement of Barton Pressure Transmitters Preliminary workplan preparation continues.
ECNs 6402 and 6439 - Pressurizer Instrumentation Relocation All work is complete except seal welding fill tees. This will be GE :EEE completed after Instrument Maintenance completes fill and calibration. A unit 2 instrument was relocated to meet Appendix R separation critoria.
ECN 6417 - Install Alternate Seal Water for Pumps CDWE Electrical drawings remain to be issued.
g,;7--- 4
~
ECNs 6491 and 6534 - ERCW Suppc-ts Drawings were received, and the workplan was written and approved.
=
All hangers for unit 2 (ECN 6534) have been completed. Three hangers remain for' unit 1.
ECN 6513 - Support of HVAC Expansion Tank The workplan was written, approved, and placed in work. Work is continuing.
ECN 6573 - Shutdown Board Alternate Feeder The workplan is in the approval cycle.
ECN 6599 - Unit 2 Shield Building Anchor Problem DNE continues to evaluate the action required for small conduit anchors.
ECN 6601 - Removal of EGTS Backdraft Dampers PMT remains to be completed.
ECN 6606 - Additional Penetration Fuses The workplan is in the approval cycle.
ECN 6610 - Modify Air Return Fan Supports Work continues on the unit 2 fans.
ECNs 6631 and 6683 - Scrubber Replacements / Modifications Preliminary workplan preparation was begun.
ECN 6636 - Replace Cable in Valve Room The workplan is in writing.
ECN 6648 - Time-Delay CCS Pump The workplan is in writing.
ECN 6661 - Upgrade of ERCW Piping The workplan remains in the approval cycle.
ECN 6667 - Delete Torque Switch MOVs The workplan is in the approval cycle. /
ECN 6681 - Supports for ERCW to Upper Compartment Coolers (Annulus) 2 Preliminary work was started on support design and workplan verification. This is continuing (see ECN 6231).
ECN 6698 - Repull 120-Volt Cables The workplan is in writing.
ECN 6701 - Modify Foxboro Recorder Latches Preliminary workplan preparation was started.
Dry Active Waste Building (DCR 1898)
Steel erection of columns and ceiling beams for the building frame has been completed, along with longitudinal purlins.
Final alignment has been made of the building frame, and corner fabrications are being installed in preparation for side insulation and sheeting. Major equipment that would create a handling problem once the roof is installed is being set.
Additional Office Buildings (DCR 2260)
Building A office area is complete with the exception of the reconfiguration of the cubicles in accordance with a design revision, installation of power poles to cubicles including electrical and communications, and minor paint touchup.
Electrical room power panels have been received and are in the process of being installed.
Potable waterlines and sewer lines see completc.
Restroom facilities and lunchroom area are complete pending light and carpet installation.
Building B final drywall plastering is in progress with an expected completion date of July 7, 1986, at which time painting and carpet and cubicle installation will begin.
Additional Office Buildings at Power Operations Training Center The east building is complete and ready for carpet installation, which is scheduled for July 7, 1986. Although no cubicles are to be installed, power poles will be installed at various locations for electrical and communications. The location design will be issued July 7, 1986.
Final drywall plastering for the west building is in progress along with exterior fire door installation.
Burnout of the potable water system is scheduled for July 11, 1986.
Septic tank ar.d drain installation is nearing completion and is due for inspection on July 10, 1986...
Welding Project Support was provided to Welding Project personnel as. requested.
Walkdown Field Verification Support
~
SMI-0-317 Concrete Edge-Distance - Complete; DNE continues to evaluate the results.
SMI-0-317 79-14 Enhancement - 145 unit 2 supports have been inspected and are being evaluated. Approximately 1,100 unit 1 supports have been inspected and are being evaluated.
Inspections continue. Approximately 60 additional supports will be added to unit 2.
Fourteen unit 2 discrepancies have been identified as requiring fieldwork.
Alternate Analysis Walkdown Work is continuing.
Unit 2__J-Tube Replacement Work was completed as scheduled.
SCR Resolution Many man-hours were spent resolving SCRs.
4 '
MODIFICATIONS ECN DCR SYS DESCRIPTION UNIT 19256 031 Replace exiting mallory I
capacitors in the FCO 7 475&476 with Maxwell Capa-I citors ITT #104857-AJ L5265 D0741 S 031
' Replace doors C-49 & C-50 0
per PT-522 Ref ECNs 5264 &
5347.
L5576 D1377 S 069 Add a double isolation valve 2
on each vent line at the floor level on ele 734 (refueling floor).
Connect the vent lines into the plant drain system pres-surizer condensate reset.
L5591 D0837 317 Redesign control circuits 2
to monitor neutral contracts on all W-2 spring return to center type switches or change to GE SBN switches.
L5667 D0674 S 063 Replace' existing 1/2" S/S 2
6000 # socket weld cap with a 1/2" 6000 # threaded lap -
SIS hot & cold leg and BIT injection flow orifices.
L5794 D1804 S 067 Replace retainer ring of 1
Asim A-516 GR.70 with a retainer ring of 304 stain-less steel for 6" 150 lb.
Do SI-Seal Butterfly v1v dwg. #17W586-24 MK# SK-6874.
Ref TACF 82-2168-6.
L5957 D1380 099 Replace the present SI reset I
timing relay, mfg. agastat -
model 2412AE with an on delay /
off delay relay. TDis (SSPS time delay).
L6209 F2588 363 Install a fire protection 2
blanket around conduits and add pyrocrete to floor hatch for fire protection.,
--n.
--e-.
MODIFICATIONS ECN DCR SYS DESCRIPTION UNIT L6529 D0972 000 Seal class 1E devices at their conduit entry with a nuclear 2(
qualified seal and reduce the size of conduit opening on other devices with RTV sealant.
L6549 D0972 S 000 Analyze junction boxes I
housing class IE component located inside containment below postulated LOCA flood level and relocate if req.
LS169 077 Documentation to revise v1v 2
marker tags to add tag num-bers for PDIS77-403,404, 405. QA chg #350 added unit 2 to WP 8432. Ref AC-449.
L6223 F2725 S 003 Repair leaking valves 1 1 524, -526 by injecting Fermonite into the bodies of 1-3-525, 527 filling valves and connecting pipe.
L6230 F2734 S 003 Cut and cap the six (6) 1 drain lines involving the removal of valves 3-504,505, 506, 507, 520, 521, 522,523, 524, 525, 526 and 527.
(FCR-2734 Cat D)
L6690 D2259 S 000 Bolt torque requirement 2
for non high strength bolts in friction type connections for supports. No predecessor ECNs.
4 Not Req D1967 S 001 Remove the tube lane 2
blocking devices from the steam generators. The low-down pipe blocker assembly shall not be removed.
1 e
i I
.._,_ _ c l_ _
2 ENVIRONMENTAL QUALIFICATION (E.Q.)
SUMMARY
n
Date: 7/1/86 Estimated Date of Coupletion SCR No.
Description ECN Engineer Workplan No. U-1 U-2 Consnents EQP 8501 Disconnect 1-and 2-HS-62-61 6524 Peters 11901 C
C U-2 QIR submitted.
EQP 8502 Replace penetrations 23 and 6490 Peters 11801, 11802, C C
Conplete QIR submitted.
48 11810, 11811 1
EQP 8503 Relocate RE-90, 273, -274 6500 Peters 11810, 11811 C N/A Conplete field verification sheets i
are in binder. No QIR needed.
i EQP 8504 Splice methods not correct N/A Stockton 80 MRs C
C Conplete QIR submitted.
1 EQP 8505 D.
N/A_
N/A N/A N/A N/A i
EQP 8506 Seal containment isolation 6514 Kimsey 11880 C
C valve EQP 8507 Rewire MOV N/A Rutledge 11866, 11853 C C
EQP 8508 JB weepholes (press) 6523 Alas 11893 C
C Conplete QIR submitted.
EQP 8508R2 JB weepholes 6709 Alas EQP 8509R1 Conduit seals 6529 Kimsey 11903, 11904 C C
l EQP 8509R2 Conduit seals 6615 N/A N/A N/A No field work remaining.
EQP 8510 Disconnect local handswitches 6527 Peters 11901 C
C s
EQP 8511 Submerged JB inside 6549 Peters 11901 C
N/A containment 4
1 1
[
1; 4
Date: 7/1/86 Estimated Date of Camletion SCR No.
Description ECN Engineer Workplan No. U-1 U-2
'Consnents EQP 8512R2 Rewire JB N/A Anburn 11855, 11856 C C
All boxes rewired.
EQP 8513 Weep holes (moisture) 6547 Alas 11898 C
C Conplete QIR submitted.
EQP 8513R2 Weep holes (moisture) 6565 Alas 11937 C
C Conplete 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 EQP 8516 Replace 2-LT-3-174 N/A Instrument N/A N/A C
Maint.
d 8
EQP 8517 ABG15 humidity control 6578 Gonzalez N/A C
EQP 8518 Submerged cables 6533 Various/6 Variot.s C
C EQP 8519 Tee drains N/A Electrical N/A C
C Couplete QIR submitted.
Maint.
EQP 8520 Expired cables 6553 Gonzalez 11902 C
C EQP 8521 Delete TB and rework splices 6550 Stockton 11914, 11915 C C
EQP 8521R1 Delete TB and rework splices 6651 EQP 8522 Rewire local panels N/A Stockton 11914, 11915 C C
EQP 8522R2 Rewire local panels N/A Instrument 12016 C
7/2 Maint.
I
Date: 7/1/86 Estimated Date of Completio_n SCR No.
Description ECN Engineer Workplan No. U-1 U-2 Comments EQP 8523. Missing bolts and washers N/A Stockton 11914, 11915 C C
and misplaced brackets EQP 8524 Change setpoints 6551 Instrument 11916 C
C Maint.
EQP 8525 Retenninate hydrogen N/A Electrical N/A C
C Canpleted by Electrical Maint.
reconbiner (MR)
Maint.
EQP 8526 Replace FSVs, U-1 1 U-2 11 6552 Mechanical 11897 C
C Mods.
I EQP 8527 Coat TB, U-1 3, U-2 8 N/A Stockton 11914, 11915 C C
(MR)
EQP 8528 Solder strain gauge Barton IMI Instrument N/A C
C QIR submitted 1/24.
transmitters Maint.
i EQP 8529 POT-30-42, -43 6554 Legg 11912 C
C 1
EQP 8530 Gasket, Namco L/5 N/A Electrical N/A C
C (MR)
Maint.
EQP 8531 Delete MOV heaters 6544 Rutledge 11866, I1853 C C'
EQP 8532 Delete L/S 1, 2-43-201, 6630 Alas N/A N/A No longer an issue.
-202, -207, and -208 EQP 8533 Delete dual voltage splice N/A Rutledge 11866, 11853 C C
,t!
)
M Date: 7/1/86 Estimated Date of Coneletion SCR No.
Description ECN Engineer Workplan No. U-1 U-2
- Comments EQP 8534 Resplice valve positioner N/A Maxwell MR C
C Conplete QIR submitted.
3-114 and -175 EQP 8535 Replace limit switches, 6556 Stockton 11927, U-2 C
C U-1 10, U-2 12 11928, U-1 EQP 8536 Valve room submergence 6561 Mechanical 11939 C
C Cap drains 6632 Mods.
C C
EQP 8536R1 Valve room submergence 6612 Electrical C
C Mods.
l EQP 8537 Rebuild or replace JB 3078 6579 Arburn N/A C
i i
EQP 8538 Replace capacitors N/A Maxwell 11977 N/A C
FCO-31-475, -476 1
1 EQP 8539 Replace capacitors N/A Instrument C
C Maint.
EQP 8540 Replace pigtails to Target 6649 Peters
=
7/15 7/15 Workplan in approval cycle.
Rock silenoid valves EQP 8541 Delete ;) rakes 6582 Branham 11980 C
N/A i
!s EQP 8542 Replace unqualified cables 6680 Hall 7/30 N/A Two cables will be replaced in accordance with a new issue.
EQP 8543 Replace JB wire N/A hrburn 11855, 11856 C C
i
[
s'
,, g
Date: 7/1/86 Estimated Date of Completion SCR No.
Description ECN Engineer Workplan No. U-1 U-2
' Comments EQP 8601 Replace 1, 2-PT-1-2A, -27A; 6588 Elkins 12014 C
7/2
' upgrade 2-PT-1-28, -278 EQP 8602 Reroute control cables for a " aa " " " " " aaaaaaaaaaa G aaa a aaaaaaa n " " aaaa No longer an issue.
1, 2-FCV-7047, -E9 EQP 8603 Replace portion of PP111B 6627 Kimsey N/A C
EQP 8604 Cable 1PL3241A not qualifieu"aa"auaanaauaaaaaaaaaaaaaaGanaa""aua"A No longer an issue.
EQP 8605 1, 2-TS-74-43, -44, -45, 6589 Branham C
C
-46 not qualified n
EQP 8606 Undervoltage concern on 6611 Rutledge 8/15 8/5 Holding for drawings fee &ater isolation valve 6676 brakes EQP 8607 Delete TB for 1, 2-PT-1-2A, 6626 Instrument 12014 C
7/2 Will work same time as EQP 8601.
-27A Maint.
EQP 8608 Enable / disable MOV brakes 6621 Rutledge 6/30 6/30 Holding for ECW 6686.
6622 6665 6686 8/13 8/13 EQP 8609 Replace cable IV79738 6618 N/A EQP is reviewing ECN for technical
~
correctness.
EQP 8611 JB has weephole in top N/A Amburn N/A C
)
Date: 7/1/06 Estimated Date of Concletion SCR No.
Description ECN Engineer Workplan No. U-1 U-2
'Consnents N/A Move surge suppression 5773 Kimsey 11883 C
C U-2 conplete. On U-1, 1-PCV-68-340 network for PORV in hold. Holding for maintenance to conplete.
EEB 8523 Penetration overcurrent 6606 Legg 7/20 7/20 During closure process, it was found that 6 circuits had not been addressed by ECNs. ECN 6606 addresses this.
1 N/A Work FCR to delete I,
5883 Hall C
C N ed SI-166.
2-PS-3-160A, -160B, -165A, e
and -165B O'
N/A Replace 1-FT-1-3A, -38, -10A, 6347 Instrument N/A C
N/A Transmitters changed need response
-108, -21A, -21B, -28A, -288 Maint.
test.
NEB 8510 Relocate LT-68-320, 6439 Carrasquillo various C
C PT-68-323, -320 Peters Remnunt 63-71,68-308 64 %
Legg 11865 C
C l
Replace LS-65-4, -5 6504 Legg 11865 N/A C
MEB 8410R3 Replace LS-77-127 6525 Legg 11865 N/A C
Delete brakes FCV-62-61 6521 Branham 11905 C
C s
EEB 8517 Replace pressure transmitter 6488 Branham 11931 C
C PDT-65-80, -82, -90, and -97 EEB 8631 Raychem splice i
lf
Date: 7/1/86
~
i Estimated Date of Completion SCR No.
Description ECN Engineer Workplan No. U-1 U-2
' Consents EQP 8612 bplace zone switches 6669 N/A C
4 EQP 8614 Weepholes in JB 6652 C
C EQP 8615 Replace FT-72-13, -34 EQP 8617 Junction box internal wiring EQP 8618 Relocate arc suppression network
}
EQP 8619 Valve room submerged cables 2
EQP 8620 Relocate steam generator level transmitters i
I i
1 j
i i %.
1
)
f 90 gl se -
i I
{
2 i
i OFFSITE DOSE CALCULATION MANUAL CHANGES t
/
i e
THIS PAGE INTENTIONALLY LEFT BLANK
. - _ _... _, _.. ~... _
TABLE OF CONTENTS
- Introduction 2
1.
Gaseous Effluents
=
1.1 Alarm / Trip Setpoints 1
1.1.1 Release Rate Limit Methodology - Ci/s 1
Step 1 1
14 A.
Noble Gases 1
B.
Iodines and particulates 4
Step 2 10 l14 1.2 Monthly Dose Calculations l14 10a
' 1.2.1 Noble Cases 11 Step 1 l13 11 Step 2 13 14 1.2.2 Iodines and particulates 14 Step 1 14 13 Step 2 16 1.3 Dose projections 16 1.4 Quarterly and Annual Dose Calculations 16 1.5 Gaseous Radwaste Treatment System Operation 16 1.5.1
System Description
16 1.5.2 Dose Calculations 16a 1
TOC-1
._.,_,_l_._--._.---,._...
~
s TABLE OF CONTEN1J (continued)
-2.
Liquid Effluents 17 2.1 Concentration 17 2.1.1 RETS Requirement 17 2.1.2 Prerele'ase Analysis 17 2.1.3 MPC - Sum of the Ratios 18 2.2 Instrument Setpoints 19 2.2.1 Setpoint Determination 19 2.2.2 Post-Release Analysis 20 2.3 Dose 20 2.3.1 RETS Requirement
'20 2.3.2 Monthly Analysis 21 2.3.2.1 Water Ingestion 21 2.3.2.2 Fish Ingestion 23 2.3.2.3 Recreation 23 2.3.2.4 Monthly Summary 25 2.3.2.5 Dose Projections 25 2.3.3 Quarterly and Annual Analysis 25 2.3.3.1 Individual Doses l
25 2.3.3.2 Populetion Doses 28 l
2.4 Operability of Liquid Radwaste Equipment 28 3.
Radiological Environmental Monitoring 30 3.1 Monitoring Program 30 3.2 Detection capabilities 30 l
3.3 Interlaboratory Comparison Program 30 13 3.4 Land Use Census 30 l
l l
l I
l TOC-2 Revision 14 l
a
- Description of Change A typographical error in Table 3.2-1 " Maximum Values for the Lower Limits of Detection (LLD)" is to be corrected.
for airborne particulate or gas should be 1 x 10 2The gross beta LLD value (1 x 10 )
8 No model chan reflected in this change; therefore, no evaluations are necessary.ges are v
fe -
P e
a A
--[~..-_.-,
-(Sheet 1 of 3)
TABLE 3.2-1 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION-(LLD)a c 1
o Airborne Particulate Analysis Water or Gas Fish Milk Food Products Sediment (pCi/1)
(pCi/1)
(pCi/m3)
(pCi/kg, wet)
(pCi/1)
(pCi/kg,wot)
(pCi/kg, dry) gross beta 4
1 X 10-2 '
N.A.
N.A.
N.A.
N.A.
./
I 11 - 3 2000 N.A.
N.A.
N.A.
N.A.
N.A.
Mn-54 15 N.A.
130 N.A.
N.A.
N.A.
I Fe-59 30 U.A.
260 N.A.
N.A.
N.A.
i Co-58,60 15 N.A.
130 N.A.
N.A.
N.A.
2n-65 30 N.A.
260 N.A.
N.A.
N.A.
Zr-95 30 N.A.
N.A.
N.A.
N.A.
N.A.
Nb-95 15 N.A.
N.A.
N.A.
N.A.
N.A.
I-131 lb 7 X 10-2 N.A.
1 60 N.A.
'Cs-134 15 5 X 10-2 130 15 60 150 Cs-137 18 6 X 10-2 150 18 80 180 Ba-140 60 N.A.
N.A.
60 N.A.
N.A.
La-140 15 N.A.
N.A.
15 N.A.
N.A.
s t
m Description of Change c
Table 3.1-2 of the SQN ODCM is to be revised by deleting Farm SU SSE.
This farm is to be deleted because milk samples are no longer available
~
3.3 miles at this location.
This change is also reflected in Figure 3.1-6.
~
Evaluation and Justification for ChanRe The change is necessary to accurately reflect the milk sampling program conducted at SQN.
Effect on the Accuracy and Reliability of Dose Calculations and_Setpoint Determinations _
This change has no effect on the accuracy or reliability of dose calculation or setpoint determinations.
s s
em 5
6 m
6 u.
- ? -
SQN TABLE 3.1-2 ATMOSPi4ERIC AND TERRESTRIAL MONITORING STATION LOCATIONS 1
SEOUOYAH NUCLEAR PLANT Location Reference Approximate Distance and
_ Number Sqmple Station Direction from Plant 2
LM-2 SQ 0.8 mile N 3
LM-3 SQ 1.3 miles SS'.'
4 LM-4 SQ 1.5 miles UE 5
LM-5 SQ 1.7 miles In:.
7 PM-2 SQ (Chester Frost Park) 3.8 miles SW s
8 PM-3 SQ (Daisy) 5.6 miles W 9
PM-8 SQ (Harrison) 8.7 miles SSW 10 PM-9 SQ (Lakeside) 2.7 miles WSW 11 RM-1 SQ (Chattanooga, Riverside) 16.7 miles SW 12 RM-2 SQ 17.5 miles NNE 13 RM-3 (Cleveland) 11.3 miles ESE 14 RM-4 (Dunlap) 19.5 miles WNW 17 Farm M 3.5 miles NNE 18 Farm J 1.3 miles IM 19 Farm IM 1.3 miles W 20 Fann EM 2.5 miles N 21 Farm BR 2.3 miles SSW 22 Farm LE 3.5 miles S
.23 Farm GO 1.7 miles E 25 Farm B (control) 43.0 miles UE 26 Farm C (control) 16.0 miles NE 27 Farm S.(control) 12.0 miles ImE Revision 14 1
._._m
,.,. + - - - ~
Figure 3.1-6 MILK A!10 VEGETAT10tl SAMPLitlG LOCAT10ftS
- k
/
h
@ s
'i y
+
I I9 cx
?
3>
c ~
.w x
D Milk and vegetation collected Miles O Vegetation only collected 0
1 2
flote: Vegetation is also collected at each air monitoring station.
Revision 14 See Figure 3.:1'll-
_ y.,.
a
5
-Description of Change Figure 3.1-7 " Milk Sampling Locations" is to be deleted.
The milk sampling locations are identified in Figure 3.1-6 with the vegetation sampling All references to Figure 3.1-7 in the text of the ODCM have been locations.
changed to Figure 3.1-6.
This deletion removes redundant information from the SQN ODCM and has no effect on the methodology or sampling program outlined in the manual.
Evaluation and Justification of Change The change will remove redundant information concerning milk sampling locations.
Effect on the Accuracy and Reliability of Dose Calculations and Setpoint Determinations This change has no effect on the accuracy or reliability of dose calculations or setpoint determinations.
O o
n--
~ ~ ' ~ '
_m
S.
Figure 3.1-7 Milk Sampling Locations
~2 Figure 3.1-7 Deleted by Revision 14 90 e
o O
s.
4
- Description of Change
~.
The word " land" is to be inserted in the phrase ".
boundary.
. nearest site
" to clarify the location descriptor as ".
boundary.
." on pages 2, 5, and 13.
nearest land site change; therefore, no evaluaticns are necessary.No model changes are reflected in this l
l e
I e
\\
4 A
f t
1 1
1
S.
7.
R:w metssral gical dIts consist of wind speed and direction measurements at 10m and temperature measurements at 9m and 46m.
8.
Dose is to be evaluated at the offsite exposure point where 2
maximum concentrations are expected to exist..
9.
Potential maximum-exposure points considered are the nearest land site boundary points (Table 1.4) in each sector.
l14 10.
A semi-infinite cloud model is used.
11.
No credit is taken for shielding by residence.
12.
Plume depletion and radioactive decay are considered.
13.
Building wake effects on effluent dispersion are considered.
14.
A sector-average dispersion equation is used.
15.
The wind speed classes that are used are as follows:
Number Range (m/s)
Midpoint (m/s) 1
<0.3 0.13 2
0.3-0.6 0.45 3
0.7-1.5 1.10 4
1.6-2.4 1.99 6
5 2.5-3.3 2.88 6
3.4-5.5 4.45 7
5.6-8.2 6.91 8
8.3-10.9 9.59 9
>10.9 10.95 16.
The stability classes that will be used are the standard A through C classifications.
The stability classes 1-7 will correspond to A=1, B=2, C=7.
17.
Terrain effects are not considered.
18.
Environmental transfer data is consistent with ITURE0/CR-1004 Equations To calculate the dose for any one of the 16 potential maximum-exposure points, the following ee.uations are used.
For determining the air concentration of any radionuclido: Revision 14
- l l
10.
P:tential maximum exposura points considersd are the nearest land site boundary points (Table 1.4) in each sector.
14 11.
Terrain effects are not considered.
12.
Building wake effects on effluent dispersion are considered Plume depletion and radioactive decay are considered for 13.
air-concentration calculations.
14.
Radioactive decay-is considered for ground-concentration calculations.
15.
Deposition is calculated based on the curves given in Figure 1 2 16.
A milk cow obtains 100 percent of her food from pasture grass 17.
No credit is taken for shielding by residence.
Equations To calculate the dose for any one of the potential maximum-exposure point the following equations are used:
s, 1.
Inhalation Equation for calculating air concentration, X, is the same as in the Noble Cas Section, 1.1.1.A.
For determining the thyroid dose rate:
D 1 x 10-6 Xi DFIt THI
=
i (1.4) 3 where:
DTHI thyroid dose rate due to inhalation, mrem /y.
=
X=
air concentration of radionuclide 1, pCi/m3 i
DFI infant inhalation dose factor, mrem /yr per pCi/cm3, t
=
(Table 1.7).
1 1 x 10-6=
m3/cm3 conversion factor.
J l Revision 14 C
N Step 2 This methodology is to be used if the calculations in Step 1 yield doses that exceed 50 percent of the applicable limits.
l13 Equations and assumptions for calculating doses to air from releases 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 land site boundary point in each 14 sector.
3.
Historical onsite meteorological data from the period 1972-1975 9
will be used.
4 All measured radionuclide releases are considered.
5.
A semi-infinite cloud model is used.
6.
Radioactive decay is considered.
7.
Building wake effects on effluent dispersion are considered.
8.
Dose factors are calculated using data from TVA's radionuclide library.
Equations Equations for calculating air concentration, X, is the same as in Section 1.1.1, step 1, part A.
Air concentrations are calculated for the site boundary in each sector.
For determining the gamma dose to air Dyn " nn XaiDFyi (1.16) i where:
Dyn = gamma dose to air for sector n, mead.
Kni = air concentration of radionuclide i in sector n, pCi/m3 DFyL= gamma-to-air dose factor for radionuclide i, :nrad/yr per pCi/m3 (Table 1.5).
t
= time period considered, yr m
Revision 14 - - - - -
~-
~ ~ ~
S.
- Description of Change ODCM page 10 under Step 2 has been revised to include methodology for Release Mix specific setpoint determination.
Evlauation and_ Justification for Change This addition is needed in'EhW 0DCM to illustrate how setpoints (gaseous) determined for releases of a known nuclide mixture.
are Methodologies are given for determining setpoints from th7 RETS dose rate limits or from the 10 CFR 50.73 concentration limita for reporting.
Effect of Change on Release Rate Limits or Calculated Doses These changes will not affect calculated doses.
Changes in gaseous release rate limits calculations have been documented in the memorandum from E. A.
Belvin to H. L. Abercrombie, dated October 30, 1985 (L61 851030 800).
O 9
4 O
d
_y e.,
y a
a St*p 2e (Initial S*towint')
The dose rate limits of interest (Specification 3.11.2.1) are:
Total Body = 500 mrem /yr 7
Skin = 3000 mrem /yr Maximum Organ = 1500 meem/yr
]
For the determination of initial setpoints, the above limits are divided by the appropriate dose calculated in step 1 yielding, Dose limit
=R Dose step 1 This ratio, R, represents how far above or below the guidelines this step 1 calculation was.
Multiplying the original source term by R will give release rates that should correspond to the dose limits given above.
Appropriate release rate limits in pCi/ see for each nuclide and release point will be provided to plant personnel for use in establishing monitor setpointst The setpoint for each gaseous ef fluent monitor will be established using plant instructions.
The general equation used by plant personnel in establishing setpoints in epm from release rate limits in pCi/see is as follows:
C = 0 x e x s x 60 v x 28320 where:
C = monitor setpoint, cpm Q = release rate limit, uCi/sec
= detector efficiency, cpm /pci/cc e
= safety factor; 0.2 for systems without s
automatic isolation; 0.5 for systems with automatic isolation 60 = sec/ min 28320 = cc/ft3 V = flow rate past the detector, cfm Step 2b (Release Mix Specific Setpoints)
When release mixes are known, setpoints are based on the dose methodology given in Step 1, disregeding the design source term mix.
Using a normalized source term (qt) for each nuclide, nuclide specific dose rates (D ) are determined independently for each nuclide using Stop 1 methodology.
L Dividing the appropriate dose rate limit above by the nuclide specific dose rate, D[,
yields.
Dose rate limit
= ct Di This ratio, ri represents how far above or below the guidelines the nuclide specific dose rate (Di) is.
by ri will give the maximum allowable release rate R[ for nuclide 1. Multiplyin 14 Revision 14
s far acch nuclida is elco calculated by an alternative methodology Rt using the reporting requirements of 10 CFR 50.73 (2 times the 10 CFR 20 Appendix B.
Table II air concentrations).
Release rate limits, Ri for each nuclide are calenlated using this methodology as given below:
Rt = (2)(MPC )(5.12 x 10-6)(10-6) i
= 1.02 x 10-11 MPCi where MPCi = the 10 CFR 20, Appendix B. Table II, air concentration, pCi/cc.
5.12 x 10-6 = worst land site boundary X/Q, s/m3 (Table 1.4).
10-6 = conversion factor, m3/cc.
The release rate limit, R. for each nuclide will be the most restrictive t
14 one calculated using both methodologies.
For a known mixture of n nuclides the release rates must be such that:
n
<1 i=1
~
Appropriate release rate limits in pCi/s for each nuclide and release point will be provided to plant personnel for use in establishing monitor setpoirts. The setpoint in counts per minute for each gaseous effluent monitor will be established using plant instructions.
The general equation used by plant personnel in establishing setpoints in epm from release rate limits in pCi/see is the same as that used in Step 2a.
1.2 Monthly Dose calculations Dose calculations will be performed monthly to determine compliance with specifications 3.11.2.2 and 3.11.2.3.
These specifications require that the dose rate in unrestricted areas due to gaseous effluents from each reactor at the site shall be limited to the following:
For noble gases, 1.
During any calendar quarter, 5 mead to air for gamma radiation and 10 mead to ir for beta radiation.
2.
During any calendar year, 10 mead to air for gamma radiation and 20 mrad to air for buta radiation.
For lodines and particulates.
1.
During any calendar quarter, 7.5 mrem to any organ.
2.
During any calendar year, 15 mrem to any organ.
-loa-Revision 14
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L6 L 85103o 8CO a.
' ?- s n-
.H L. Abercrombie, Site' Director, NUC PR, Sequoyah
~
E. A. Belvin, Manager, Radiological Health ant T
, 401 UBB-C OCT 3 01985
~
SEQUOYAH. NUCLEAR PLANT - GASEOUS RELEAS TE LIMITS
References:
1.
M$morandum from G.
F.
Stone to H. J.
Acceptance Criteria for"Sequoyah Nuclear Pla
- Green, Plant Gaseous Releases,"Sequoyah' Nuclear (LO 810313 228) dated March 11, 1981 2.
Memorandum from E. A. Belvin to H. J
. Green, '
Technical Specifications," dated November 1, 1982 (LOO 821104 763)
Radiological Health Technical Assistance secti the nuclide specific on has revised Nuclear Plant (SQN). gaseous release rate limits for Sequoyah (attached) are mix independent and are bThese updated release rat limits given in Radiological Effluent Technic lased on the dose r 1(IETS ) 3.11.2.1.
a Specification The revised release rate limits, which ar revisions to the caseous Effluent Licensing Code (GEL e the result of are intended to supersede the limits given in ref Gaseous release rate limits for ' initial t i /
C),
determinations have'been previously provided (
erence 1.
r p set-point and are based on the CELC revisions.
reference.2)
A comparison of thh revised release rate li i contained in reference 1 indicates thatm ts with those short-lived Kr-89 and Xe-137. gases have not been significa decreased 'by about a facter of 3 5 Limits for these two nuclides
, - except for the particul However,ates are generally lower by a factor of 1 to 11 Release factor of 1 to 5.the revised limits for iodines are hi h g er by a
~
determined based on the reporting rein addition, rate limits have been (2 times the 10 CFR quirements of 10 CFR 50.73 unrestricted areas).20 Appendi:: D.
These limits are also included in th
. attachments.
In general a factor of about 1 to 5.6,for ncble gases are more,re the 10 CFR 50.73 release rate linits except for Xe-137.e than the RETS limits by the 10 CFR 50.73 limits for iodineslimit is more re of about 27.Its 10 CFR 50.73 Exceptions are Br-84, general, significantly less restrictivand p
- Further, Br-85, Rb-88, e than the RETS limits.
and Pr-144.
4
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2 H. L. Abercromb.ie
~
.y, SEQUOYAH MUCLEAR PLANT - GASEOUS RELEAS A73 gygy7s l1mits as are thathe 10 CFR 50.73 rel are no in tan aneou 10 CFR 50.73 limits are 14 to be averaged over a one U4 +.s,or reco ar-,S limits.
Th'*
--b1 v
hour ' time p'riod.
tc and are e
If we can be of furth -
y be directed oRegfs'N ob t me k.ow.
C
'a oog y
e i
E.
A.
Belvin
~
RMN:LAs Attachments cc (Attachments):
NUC PR RIMS, 1520 CST 2-C Don Amos' NUC PR' Sequcyah RARC Fil
/
bc (Attachmen s).
B. M. Eiford, 401 UBB-C)
C. E. Rent, 401 UBB-C O
e
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l l
l
4 s.
a.
ATTACHMENT 1
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~
S_EOUOYAH NUCLEAR "LANT - NOBLC CAS REL P
~
10CFR20 RETS 10CFR50.73 Nuclide Limit (uci/s)
Limit
- MFC Ar-41
_ (uci/cel
~
Kr-85s 1.3 (+4)
__ (uCi/s)
,. -8.7 (+4) 4(-8) 1.6 (+4) 1(-7)
Kr-87 4.3 (+5) 3.9 (+4) 3(-7)
Kr-88 2.0 (+4)
- 1. 2 (+5 )
2(-8)
Kr-83 7.2 (+3)
'2(-8) 7.8'(+3)
Xe-131m 6.2 (+4) 7.8 (+3) e 3(-3)
Xe-133s 9.0 (+5) 1.2 (+4) 4(-7)
Xe-133 3.9 (+5) 1.6 (+5) 3(-7)
Xe-135s
.3.3 (+5) 1.2 (+5)
Xe-135 4.1 (+4) 3(-7) 1.2 (+5) i 3(-8) 1.2 (+4).
Xe-137 5.2 (+4)
Xe-138 3.2 (+5) 1(-7) 3.9'(+4) 3(-3) 2.1 (+4) 1.'2 (+4) 3(-8) 1.2 (+4)
- Limit (pCi/s) = 2 x HPC (pci/cc) / 15 12 x 10~6 3
~6 3
,s/m ][10 m /c'c]
6 3
Were 5.12 x 10 s/m SQN - CDCM.
= vorst site boundary X/Q listed in the I
e i
.s ATTAC10ENT 2
- SEOU OYAH NUCLEAR PLANT - ICDINE/ PART
,,g Nuclide RETS 10CFR20 MFC Limit _(uCi/sl (pci/ce) 10CFR50.73 H-3 Limit * (uci/s)
C-14 3.3 (+4)
' Na-24 4.0 (+1) 2(-7)
Cr-51 1.1 (+3) 1(-7) 7.8 (+4)
Mn-54 1.4 (+3) 5(-9) 3.9 (+4)
Fe-59 1.1 (+1) 8(-8) 2.0 (+3)
Co-58 1.4 (+1) 1(-9) 3.1 (+4),
Co-60 2.4 (+1) 2(-9) 3.9 (+2)
Z -65 1.7 (+0) 2(-9) 7.8 (+2)
Br 2.9 (+0) 3(-10) 7.8 (+2)
Br-85 5.2 (45) 2(-9) 1.2 (t2)
Eb-88 9.1.(+7) 3(-8) 7.8 (+2) 3.5 (+5) 3(-8) 1.2 (+4) 4.7 (-1) 3(-8) 1.2 (+4)
Sr-89 Sr-90 Sr-91 8.3 (-3) 3(-10) 1.2 (+4)
Y-90 1.1 (+3) 3(-11) 1.2 (+2)
Y-91m 1.7 (+2) 9(-9) 1.2 (+1)
Y-91 7.8 (+4)'
3(-9) 3.5 (+3)
Y-93 5.7 (+0) 6(-7) 1.2 (+3)
Zr-95 5.3 (+2) 1(-9) 2.3 (+5)
Nb-95 1.2 (+1) 5(-9) 3.9 (+2)
Mo-99 1.2 (+1) 1(-9) 2.0 (+3)
Tc-99:s 1.6 (+2) 3(-9) 3.9 (+2)
Ru-106 3.6 (+4) 7(-9) 1.2 (+3)
Sb-124 3.2 (-1) 5(-7) 2.7 (+3)
Te-132 7.7 (+0) 2(-10) 2.0 (+5 )
I-131 1.3 (+2) 7(-10) 7.8 (+1)
HI-131 1.6 (-1) 4(-9) 2.7 (+2)
I-132 1.2 (+1) 1(-10) 1.6 (+3) 3.9 (+1)
MI-132 l'.1 (+3) 1(-10) 1-133 1.1 (+3) 3(-9) 3.9 (+1)
HI-133 7.1 (+0) 3(-9) 1.2 (+3) 1-134 5.2 (+1) 4(-10) 1.2 (+3)
MI-134 5.4 (+3) 4(-10) 1.6 (+2) 1-135 5.0 (+3) 6(-9) 1.6 (+2)
HI-135 2.4 (+2) 6(-9) 2.3 (+3)
Cs-134 2.6 (+2) 1(-9) 2.3 (+3)
Cs-136 3.7 (-1) 1(-9) 3.9 (+2)
Cs-137 1.6 (+1) 4(-10) 3.2 (+2)
Ba-140 3.6 (-1) 6(-9) 1.6 (+2) 2.3 (+3)
La-140 4.3 (+1) 5(-10)
Cc-141 2.7 (+2) 1(-9) 2.0 (+2)
Cc-144 3.6 (+1) 4(-9) 3.9 (*2)
Pr-143 9.9 (-1) 5(-9) 1.6 (+3)
Pr-144 6.3 (+1) 2(-10) 2.0 (+3)
Np-239 7.6 (+4) 6(-9) 7.8 (+1) 8.1 (+2) 3(-8) 2.3 (t3) 2(-8) 1.2 (+4)
- Limit 7.8 (+3)
(pci/s) = 2 x MPC (pci/cc) / (5.12 x 10.6 3
~6 3
s/m ][10 m /cci
S
}
=.
i.
TENNESSEE VALLEYi AUTHORITY-Sequoyah Nuclear Plant P. O. Box 2000-i Soddy-Daisy, Tennessee -37379 July 14, 1986 8
Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC-20555 i-
~Gentlement SEQUOYAH NUCLEAR PLANT -' MONTHLY OPERATING REPORT - JUNE 1986-Enclosed is the June 1986 Monthly Operating Report to NRC for Sequoyah Nuclear Plant.
Very truly yours, TENNESSEE VALLEY AUTHORITY J.
J Lv 4
P. R. Wallace Plant hanager Enclogure cc (Enclosure):
Director, Region II i
Nuclear Regulatory Commission
{
Office of Inspection and Enforcement Suite 3100 101 Marietta Street Atlanta,' Georgia 30323 (1 copy)
Director, Office of Inspection and Enforcement Nuclear Regulatory Commission Washington, DC 20555 (10 copies)
Mr. A. Rubio Electric Power Research Institute P. O. Box 10412 Palo Alto, California 94304 (1 copy)
INPO Records Center Suite 1500 1100 circle 75 Parkway Atlanta, Georgia 30339 (1 copy)
Ml Mr. K. M. Jenison, Resident NRC inspector r'I O&PS-2, Sequoyah Nuclear Plant 1983-TVA 5OTH ANNIVERSARY An Equal Opportunity Employer