ML20148E553

Monthly Operating Repts for Dec 1987

ML20148E553
Person / Time
Site:	Sequoyah
Issue date:	12/31/1987
From:	Dupree D, Shawn Smith TENNESSEE VALLEY AUTHORITY
To:	NRC
References
NUDOCS 8801260059
Download: ML20148E553 (63)

Text

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.p TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION "DECEMBER 1987" UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 l

UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 Submitted by:

h S. J. ymith, P1' ant Manager I

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TABLE OF CONTENTS Page I.

Operational Summary Performance Summary 1

Significant Operational Events 1

Fuel Performance and Spent Fuel Storage Capabilities 2

PORVs and Safety Valves Summary 2

Special Reports 2-3 Licensee Events 4-7 Offsite Dose Calculation Manual Changes 8

II.

Operating Statistics A.

NRC Reports Unit One Statistics 9-11 Unit Two Statistics 12-14 B.

TVA Reports Nuclear Plant Operating Statistics 15 Unit Outage and Availability 16-17 Reactor Histogram 18 III. Maintenance Summary Electrical Maintenance 19-20 Instrument Maintenance 21-24 Mechanical Maintenance 25-28 Modifications 29-42 IV.

Offsite Dose Calculation Manual Change i

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Vy OPERATIONAL

SUMMARY

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.g FERFORMANCE

SUMMARY

December 1987 The following summary describes the significant operational activities for the month of December.

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 design control review, configuration control updating, and resolution of significant employee concerns. Outage related maintenance and modifications are being performed. Unit I has been off-line 861 days. Unit 2 has been off-line 862 days. Preparations are underway for unit 2 alignment and mode 4 verification.

SIGNIFICANT OPERATIONAL EVENTS Unit 1

_ Date Time Event 12/01/87 0001E The reactor was in mode 5.

The administrative shutdown due to design control review, configuration control updating, and resolution of significant employee concerns continues.

12/31/87 2400E The reactor was in mode 5.

The administrative shutdown due to design control review, configuration control updating, and resolution of significant employee concerns continues.

Unit 2 Date Time Event 17/01/87 0001E The reactor was in mode 5.

The administrative shutdown due to design control review, configuration control updating, and resolution of significant employee concerns continues. Preparations arn underway for system alignment for mode 4 shakedown.

17/31/87 2400E The reactor was in mode 5.

The administrative shutdown due to design control review, configuration l

control updating, and resolution of significant employee concerns continues. Preparations are underway for system alignment for mode 4 shakedown.

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FUEL PERFORMANCE Unit 1 The core average fuel exposure accumulated during December was 0 MWD /MTU with the total accumulated core average fuel exposure of 0 MWD /MTU.

Unit _2 The core average fuel exposure accumulated during December was 0 MWD /MTV with the total accumulated core average fuel exposure of 8097.51 MVD/MTU.

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 ur.available due to an instrumentation conflict.

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 December 1987.

SPECIAL REPORTS The following special reports were submitted to NRC in December 1987.

87-21 Fire door C-53 was nonfunctional for an interval greater than seven days. This was anticipated for the installation of bullet-resistant doors in accordance with ECN L6860. Door C-53 is located in the control building, elevation 732.0.

This work is scheduled for completion on January 31, 1988.

8/-21 This revision reflects a date change for the corrective actions to Rev 1 be completed.

81-22 On November 28, 1987, a planned extended breach for removal of fire retardant pyrocrete around a duct between the cable spreading room and the MCR exceeded the seven-day TS limit. This was required for the performance of ECN L6860 which was issued to fulfill 10 CFR 73.55, "Requirements for Physical Protection of Licensed Activities in Nuclear Power Reactors Against Radiological Sabotage."

Also, WP 12603 was issued as part of ECN L6860, which called for the removal of pyrocrete from around two ducts. The breach was scheduled to be returned to functional status by December 19, 1987.

87-23 Fire door C-37 was inoperable greater than seven days. This was determined ay an investigation that revealed the door-latching mechanism and door handle were nonfunctional. Door C-37 is located in the control building, elevation 732.0, north end. A new door was installed by ECN L6860 to fulfill requirements in accordance with 10 CFR 73.55, "Requirements for Physical Protection of Licensed Activities in Nuclear Power Reactors Against Radiological Sabotage."

The scheduled completion date for door C-37 was December 19, 1987.

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SPECIAL REPORTS 87-23 This revision reflects a date change to the corrective action.

Rev'1 87-12 ' This revision provides additional corrective actions related to Rev 1 meteorological instrumentation being inoperable greater than seven days.

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.s I.ICENSEE EVENT REPORT (S) i The following licensee event reports (LERs)' were reported to the Nuclear Regulatory Cornission in December 1987.

Description of Event

_.LER 1-87501 On December 7, 1987, at 0230E, a Modifications Group employee.with-a visitor's badge was discovered by an NSS officer inside the vital area without an escort. The individual had just entered door A-62, elevation 690 penetration room in the auxiliary building. The officer posted at the door noticed the visitor without an escort and immediately detained him. The escort was located several minutes later and also detained. The visitor was separated from the escort approximately ten minutes. Both were escorted out of the vital area for questioning. A search was conducted for signs of tampering and suspicious activity. None were found. 'The NSS supervisor. questioned both individuals and obtained statements, then instructed both on proper escort / visitor procedures. This event was caused by a personnel error for failure to follow approved procedures.

1-87072 On November 10, 1987, a PRO was initiated which concluded that several of the ESF coolers had insufficient air flow to maintain temperatures within the EQ temperature profiles. This deficiency was discovered through a calculation review program which found that improper design inputs were used in the calculations, resulting in inadequate cooler design parameters. It is not considered to have a significant safety impact based on current plant conditions and because lower cooling water temperatures exist than those used in the design calculations. The root cause was attributed to the lack of an adequate design control program at the time the calculations were performed. Recurrence of the root cause is prevented through the use of Nuclear Engineering Procedures.

Corrective actions are being performed to increase cooler air flow rates through further opening of air dampers, cleaning cooler coils, and possibly some changes in fan motors and duct work configuration. Future plans include filtration systems installed on the cooler coils and a maintenance program to ensure that they remain clean.

1-87073 On November 10, 1987, it was determined that under certain conditions, the CCPs may not start using the manual handswitch in the MCR. The control logic for manually starting the CCPs contains an interlock that requires the AOP to start first to increase the CCP oil pressure before allowing the CCP to start. However, since the AOPs and asssociated interlocks have not been qualified in accordance with Class IE standards, they may not be available following an accident. Without them, the associated CCP cannot be started from the manual handswitch in the MCR and may not be available to mitigate the consequences of postulated accident. The event was caused by an inadequate design review of information received from NSSS vendor.

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s Description of Event

, LER 1 87073 TVA has analyzed this event and determined that alternate methods (cont) of starting the CCPs are available and they have been capable of performing their designed safety function. TVA will replace the subject AOP motors and low oil pressure interlocks with EQ components or modify the start circuitry of the CCP to exclude these components from the subject circuitry. The modifications will occur before restart of each respective unit.

1-87075 On December 3, 1987, it was determined that revision 14 of SI-118, "Motor-Driven Auxiliary Feedwater Pump and Valve Automatic Actuation," did not completely test the AFW bypass level control valves (BPLCVs) as required by TS 4.7.1.2.b.1.

Ine procedural deficiencies were discovered during the initial implementation of an upgraded SI Review Program and documented on PRO 1-87-129, initiated on March 25, 1987. The initial evaluation of the PRO resulted in a determination of "not reportable" based on the evaluation that the intent of the TS was met.

However, an audit conducted by an NRC Inspector revealed that the evaluation was incorrect. The condition of not meeting the TS SR was determined to be an incomplete test procedure, which was caused by an inadequate SI Review Program in place at the time SI-118 was written. The incorrect reportability evaluation has been attributed to a misunderstanding of the necessary steps required to i

test all operational modes of the AFW BPLCV by the reviewer i

evaluating it for reportability. As corrective action, the procedure was revised to completely test the AFW BPLCVs and this event has been reviewed with personnel responsible for reportability evaluations. All AFW BPLCVs for each unit will be tested prior to mode 3.

1-87071 On December 7, 1987, a condition was identified that could result in bypass leakage following a design basis LOCA. The hydrogen analyzer system (HAS) installed in each unit utilizes a small amount of control air to act as a reagent gas. A sample from the containment atmosphere is mixed with the reagent gas in the hydrogen analyzer module (located in the annulus inside the reactor building), analyzed for hydrogen content, and returnod to containment. During the review of an HAS-related ECN, the current HAS design represented a potential pathway for radionuclides to escape to the environment. The HAS isolation valves located inside containment are air-operated valves that fall in the "open position." If a LOCA occurred concurrent with a single failure of one train of control air, the containment pressure would eventually exceed the pressure in the control air line feeding reagent air to the hydrogen analyzer module. Radionuclides from the containment atmosphere could then be forced back through the control air line and be released to areas of the auxiliary building not covered by the ABGTS. The event was caused by an inadequate design control process that was in place when the HAS containment isciation system was installed. SQN has subsequently implemented a design change improvement program that has resulted in significant improvements j

to the design change process.

In addition, TVA will replace the l

HAS isolation valves inside containment with "fall closed" solenold-operated valves, and replace the control air supply with air bottles that will maintain the reagent air pressure greater than the maximum predicted containment pressure.

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3 Description of Event 2-87008 On November 8, 1987, a train "A" CVI occurred on unit 2.

At approximately 0320E, an instrument malfunction alarm was noticed on the lower containment lower compartment (2-RM-90-106).

Operations personnel determined that a spurious high radiation spike had occurred at approximately 0230E. This spike exceeded the RM trip criteria, thus a CVI and a malfunction alarm were generated.

Maintenance personnel determined that EMI was generated by the low sample flow switch.

Investigation into this event and three other CVIs revealed that the ground was not secured properly. The ground was secured and steps were taken to recreate the induced EMI, however, no spikes could be generated.

SQN will incorporate procedures in sis for routine inspection of detector cables to ensure proper ground, as well as ensuring that all TS RM cables are secured.

2-87009 This report combined two events that were similar.

On December 5, 1987, two CVIs occurred at approximately 0911E and 1553E, respectively. An investigation revealed that welding and grinding were being performed, resulting in the clogging of the prefilters of the RMs causing a low flow condition.

This activated 2-RM-90-106 sample low flow switch.

TVA believes this actuation induced an EMI spike to the RM detector cable. This spike exceeded the trip criteria, generating the CVI.

Immediate corrective actions have been initiated that include the changing of prefilters every four hours, and suspending welding and grinding. SQN is further investigating this by assigning a special task force to determine the root cause. Suggested corrective action to be completed by February 27, 1988.

1-87042 This revision provided additional information regarding fire pumps Rev. I starting during a LOCA i.nder Analysis of Condition and Corrective Action.

2-86011 This revision was to change the corrective action, the corrective Rev. I action due date, and to clarify the root cause concerning a CVI caused by EMI on RM 2-RM-90-106 due to personnel error.

o ABBREVIATIONS 1.

ABGTS - Auxiliary Building Gas Treatment System 2.

ABI

- Auxiliary Building Isolation 3.

AFW

- Auxiliary Feedwater 4.

AOI

- Abnormal Operating Instruction 5.

BAT

- Boric Acid Storage Tank 6.

BIT

- Boron Injection Tank 7.

CAQR - Condition Adverse To Quality Report 8.

CCP

- Centrifugal Charging Pump 9.

CCS Component Cooling System 10.

CRI

- Control Room Isolation 11.

CREV - Control Room Emergency Ventilation System 12.

CSS

- Containment Spray System 13.

CVI

- Containment Ventilation Isolation 14.

D/G(s)

Diesel Generator (s) 15.

DCR

- Design Change Request 16.

DNE

- Division of Nuclear Engineering 17.

ECCS - Emergency Core Cooling System 18.

ECN

- Engineering Change Notice

~19.

EGTS

- Emergency Gas Treatment System 20.

EMI

- Electromagnetic Interference 21 EQ

- Environmentally Qualified / Environmental Qualification 22.

ERCW - Essential Raw Cooling Water 23.

ESF

- Engineered Safety Feature 24.

FCV

- Flow Control Valve 25.

FSAR - Final Safety Analysis Report 26.

IMI

- Instrument Maintenance Instruction 27.

LCO

- Limiting Condition for Operation 28.

LOCA - Loss Of Coolant Accident 29 MCR Main Control Room 30.

NSS Nuclear Safety Service

31..NSSS - Nuclear Steam Supply System 32.

PORC Plant Operation Review Committee 33.

PRO

- Potential Reportable Occurrence 34.

RCS

- Reactor Coolant System 35.

RHR

- Residual Heat Removal 36.

RM Radiation Monitor (RAD Monitor / RAD MON) 37.

RWST - Refualing Water Storage Tank 38.

SCR

- Significant Condition Report 39.

S/G(s)- Steam Generator (s) 40.

SI

- Surveillance Instruction /or Safety Injection 41.

SOI

- System Operating Instruction 42.

SQN

- Seguoyah Nuclear Plant 43.

SR

- Surveillance Requirement 44 SSPS - Solid State Protection System 45.

TACF - Temporary Alteration Control Form 46.

TI

- Technical Instruction 47.

TS(s) - Technical Specification (s) 48.

WP

- Workplan 49.

WR

- Work Request

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'o 0FFSITE DOSE CALCULATION MANUAL CHANGES No changes were made to the Sequoyah Offsite Dose Calculation Manual (ODCM) in December 1987.

While investigating the root cause of revision 16 of the ODCM not being submitted in this report within TS time limits (PRO-1-87-451), it was discovered that revision 15 has not been submitted with the monthly operating report.

Rorision 15 to the ODCM is included in this report (Section IV).

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OPERATING STATISTICS (NRC REPORTS)

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OPERATING DATA ~ REPORT DOCKET NO. 50-327 DATE JANUARY 08, 1988 COMPLETED DY D.C.DUPREE TELEPHONE (615)870-6722 OPERATING STATUS

_1.

UNIT NAME: SEGUOYAH NUCLEAR PLANT, UNIT 1

NOTES:

2.

REPORT PERIOD: DECEMBER 1987 3.

LICENSED THERMAL POWER (MWT):

3411.0 4.

NAMEPLATE RATING (GROSS MWE):

1220.6 5.

DESIGN ELECTRICAL RATING (NET MWE):

1148.0 6.

MAXIMUM DEPENDADLE CAPACITY (GROSS MWE):

1183.0 7.

MAXIMUM DEPENDADLE CAPACITY (NET MWE):

1148.0 8.

IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMDERS 3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS:

9.

POWER LEVEL TO WHICH RESTRICTED,IF ANY(NET MWE):

10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YR.-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 744.00 0760.00 D7001.OO

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

13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

14. HOURS GENERATOR ON-LINE O.00 0.00 23781.13

15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

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

17. GROSS ELECTRICAL ENERGY GEN. (MWH) 0.00 0.00 25976386.00

18. NET ELECTRICAL ENERGY GENERATED (MWH)

-4672.00

-48236.00 24G54323.00

19. UNIT SERVICE FACTOR O.00 0.00 4f.72

20. UNIT AVAILABILITY FACTOR O.00 0.00 41.72

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 37.98

22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 37.98

23. UNIT FORCED OUTAGE RATE 100.00 100.00 50.51

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

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

STARTUP IS UNDETERMINED AT THIS TIME PENDINC DESIGN CONTROL REVIEW, CONFIGURATION CONTROL UPDATING, AND RESOLUTION OF SIGNIFICANT EMPLOYEE CONCERNS.

NOTE 1 HAT THE THE YR. -TO-DATE AND CUMULATIVE VALUES HAVE DEEN UPDATED.

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'f SEQUOYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL DOCKET NO. : 50-327 UNIT : ONE DATE :-JANUARY 05,1988 COMPLETED BY : D.C.DUPREE TELEPHONE : (615)870-6722 MONTH: DECEMBER 1987 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe Net)

DAY (MWe Net)

{

01 0

17 0

02 0

18 0

I 03 0

19 0

,i i

04 0

20 0

l 1

t 05 0

21 0

1 06 0

22 0

07 0

23 0

08 0

24 0

09 0

25 0

10 0

26 0

11 0

27 0

12 0

28 0

13 0

29 0

14 0

30 0

15 0

31 0

16 0

. ~..

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.-

50-327 UNIT NAME. Sequoyah One DATE January v.-1988 COMPLETED BY D.-C.

Dupree REPORT ?!0 NTH DECDIBER 1987 TELEPHONE (615) 870-6544 u

oyf Licensee g a,.

Cause & Corrective cg N

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73m Event ug g7 Action to No.

Date o

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gue Report #

go gu Prevent Recurreace 5~

$55 R

1 870101 F

744 F

4 Design Control, Configuration Updating, and Employee Concerns.

1F: Forced 2

3Hethod:

4 Exhibit G-Instructions Reason:

S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-!!aintenance or Test 2-Manual 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-Administrative

~5-Reduction 5 Exhibit I-Same Source G-Operational Error (Explain) 9-Other

!!-Other (Explain)

OPERATING DATA REPORT s

DOCKET NO. 50-328 DATE JANUARY 08, 1988 COMPLETED DY D.C.DUPREE TELEPHONE (615)870-0722 OPERATING STATUS 1.

UNIT NAME: SEQUOYAH NUCLEAR PLANT, UNIT 2

NOTES:

2.

REPORT PERIOD: DECEMBER 1987 3.

LICENSED THERMAL POWER (MWT):

3411.0 4

NAMEPLATE RATING (GROSS MWE):

1220.6 5.

DESIGN ELECTRICAL RATING (NET MWE):

1148.0 6.

MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):

1183.0 7.

MAXIMUM DEPENDABLE CAPACITY (NET MWE):

1148.0 8.

IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS:

9.

POWER LEVEL TO WHICH RESTRICTED, IF ANY(NET MWE):

10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YR.-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 744.00 0760.00 48961.00

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

13. REACTOR RE3ERVE SHUTDOWN HOURS 0.00 0.00 0.00

14. HOURS GENERATOR ON-LINE O.00 0.00 21494.22

15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

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

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

18. NET ELECTHICAL ENERGY GENERATED (MWH)

-4413.00

-S9378.00 22508145.60

19. UNIT SERVICE FACTOR O.00 0.00 43.90

20. UNIT AVAILADILITY FACTOR O.00 0.00 43.90

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 40.04

22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 40.04

23. UNIT FORCED OUTAGE RATE 100.00 100.00 51.22

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:

PFEPARATIONS ARE NOW UNDERWAY FOR SYSTEM ALIGNMENT, HEATUP, AND RETURN TO SERVICE IN THE NEAR FUTURE.

i NOTE THAT THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE DEEN UPDATED.

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SEQUOYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL DOCKET NO. : 50-328 UNIT : TWO DATE : JANUARY 05,1988 COMPLETED BY : D.C.DUPREE TELEPHONE : (615)870-6722 MONTH: DECEMBER 1987 AVERAGE DAILY POWER LEVBL AVERAGE DAILY POWER LEVEL DAY (MWe Not)

DAY (MWe Net) 01 0

17 0

02 0

18 0

03 0

19 0

04 0

20 0

05 0

21 0

06 0

22 0

07 0

23 0

08 0

24 0

09 0

25 0

10 0

26 0

11 0

27 0

12 0

28 0

13 0

29 0

14 0

30 0

15 0

31 0

16 0

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DOCKET NO.

50-328 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT I4AME Seouovah Two DATE January 9.

1988 COMPLETED BY D. C.

Dupree TELEPHONE (615) 876-6544 REPORT MONTH DECEMBER 1987 R

m Cause & Corrective gg g

oy Licensee go, Action to No.

Date g

gg ygg Event g7 gy o

Prevent Recurreace y

3o g

ggM Report #

go gu 5~

$N$

R Design Control, Configuration Updating, and 1

873101 F

744 F

4 Employee Concerns.

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Exhibit C-Instructions 4

2 1F: Forced Reason:

1-Manual for Preparation of Data S: Scheduled A-Equipment Failure (Explain) 2-Manual Scram.

Entry Sheets for Licensee B-!!aintenance or Test 3-Automatic Scram.

Event Report (LER) File C-Refueling 4-Cont. of Existing (NUREG-0161)

D-Regulatory Restriction E-Operator Training & License Examination Outage 5-Reduction F-A.!ministrative sExhibit I-Same Source 9-Other G-Operational Error (Explain)

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H-Other (Explain)

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• 4 OPERATING STATISTICS (TVA REPORTS) l l

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i TvA naro uw.ss NUCLEAR PLANT OPERATING STATISTICS

.l Sequoyah Nuclear Plant i

Period Hours 7bb Month December 87 39 Item No.

Unit No.

UNIT ONE UNIT TWO PLANT

]

Averaoe Hourly Gross Load. kW O_

0 0

2 Maximum Hour Net Generation. MWh 0

0 0

3 Core Thermal Eneroy Gen. GWD (t)2 0

0 0

4 Steam Gen. Therrnal Energy Gen., GWD (t)2 0

0 0

8 5

Gross Electrical Gen., MWh 0

0 0

5 ti Station use, MWh 4,672 4,413 9,085 h

7 Net Electrical Gen., MWh

-4,672

-4,413

-9,085 5

8 Station use, Percent N/A N/A N/A 9

Accum. Core Avg. Exposure MWD / Ton!

0 0

0 10 CTEG This Month,106 BTU 0

0 0

11 SGTEG This Month,106 BTU 0

0 0

12 13 Hours Reactor Was Critical 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 Avail. Factor. Percent 0,0 0.0 0.0 4

C 18 Turbooen. Avail. Factor. Percent 0.0 0.0 0.0 h

19 Reactor Avail Factor. Percent 0.0 0,0 0.0 0

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 3

24 Gross Heat Rate, Blu/kWh N/A N/A N/A j

25 Net Heat Rate, Blu/kWh N/A N/A N/A 3

26 D

27 g

29 Throttle Pressure, psig N/A N/A N/A 29 Throttle Temperature. 'F N/A N/A N/A d

30 Exhaust Pressure, InHg Abs.

N/A N/A N/A f

31 Intake Water Temo., 'F N/A N/A N/A 32 33 Main Feedwater, M lb/hr N/A N/A N/A i

34

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35 36 37 Full Power Capacity, EFPD 404.86 363.65 768.51 38 Accum. Cycle Full Power Days, EFPD 0.0 210.8416 210.8416 i

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33 Oil Fired for Generation, Gallons 14,190 5

40 Oil Heatino Value. Btu / Gal.

138,000 41 Deut! Generation. MWh 215 a?

Max. Hour Net Gen.

Max. Day Net Gen-Load MWh Time Date MWh Date Factor, %

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43 N/A N/A N/A N/A N/A N/A Remarks: IFor GFNP this value is MWD /STU and for SQNP and WRNP this value is MWD /MTU.

j 2(t) indicates Thernial Energy.

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100 9e Ao 70 -

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6x 20 10 0 --

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12 16 20 24 28 32 DECEWLER 1987 F

' 4

SUMMARY

OF MAINTENANCE ACTIVITIES

I e

O

• +

6 L

MAINTENANCE

SUMMARY

(ELECTRICAL) i r

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ELECTRICAL HAINTEMMCC 50NTHLY $UnnARY 01-12-88 Coni 8 CORRECTIVE ACTIDH.,...

MR2, U FMC SYS AMRESS. DATE.,. DESCRIPTION....

F203945 2 !.CIC 313 OW3 M/06/87 2 0CIC-313-0W3,PREAKER FAILED TRIP BREMER FAILED IHsfANTMECUS TRIP TEST.

. IEst DN 86 31-275.2 PERFDRED SI-275.2 DN THE NEW BREMER.

INSTALLED NEW BREMER PED SI-275.2.

B2097710 0010 030 5016 07/21/87 0-itiC-030 5016,DREAKER FAILED TEST DN SI-275.2 DN 8 5 IF 11-275.2 0221590 2 GEND 082 0002A 09/22/87 2-GENS-082-0002A-A, REPLACE FUtt ELOCKS FOR 2-FU3-82-TV2-A MD 2-FU3-82-TV1-A 0221188 0 ItiB 311 0028A 05/14/87 0-SCTB-311-00284 B,REtti AMPTECTIII 10 THE RE0'JIRED $ETTING FER DWS83591A27 i:2231301 BCfD 067

%90 09/14/871-BCTD-067-%90-B,EnWPRDn],$iRAIER HAT NO POWER WITH BRK CLOSED B2235481 GEND 082 0001B W/29/871-CENB-082-C0018,EwNPRDn],aIn DIESEL CENERATOR FAIL TO ACHIEVE 58.8 H2 02849551 ItT A 067

%3610/20/871-BCTA-067-%34 A,EnNFRDn],THIS l#EAKER WILL N01 DPEReit FIOl THE CONTROL EOCM OR IN Tile TEST POSITICH, THE CHMCING

$PRINC DOES NOT APPEAR 10 ft CHMGINC.

0206327 2 MT1D 067

%9010/22/87 2-MTRB-067-%90-B,ERMPRDal,TE STRA!FER WILL NOT IACKWASH APPEAR $ TO BE M ELECTRICAL PROBLD1-VED FUSES OK MD DUEn0 ADS RESET-If N01 ELECTRICAL TRANSFER TO APPROPRIATE ![CTION. NOTE tiRh HAS A HI DP -6 PtID i

aIC1RICAL MAINTEMANCE CONTHLY SlmMRY 01-12-88 COnP rR2 U mtC SYS et0RESS. DATE.

DESCRIPTION.

CORRECTILT ACTION.

I:2700? 0 t;it 026 000M 07/24/37 0-0CTB-026-00%A-B, min 5010R CONTINUE! TRIP riCHANISM SPRING hAD SLIPPED OFF.

TURN - SPRING WILL NJT CHARGE 8 DiUT REISTALLED TRIP ECHMIS!15TRING MD MOTCH tif. FUST EE D3HE IIFCRE SI-26 CM EREMER OPERATED FROPERLY.

I:E RUN.

I 1

l 9

• 4 MAINTENANCE

SUMMARY

(INSTRUMENTATION) i l

i l

l 1

1 1

INSTRUMENT MAINTENANCE MONTHLY REPORT FOR DECEMBER 1987 COMMON 1,

Continued work on' auxiliary boilers to improve reliability of controls.. Initiated TACF 0-87-036-12 and DCR 2361 to modify the fuel oil system to improve light-off capabilities. Also participated on special task force developed to investigate "puff" occurring on auxiliary boiler B on December 8, 1987.

2.

During investigative testing to determine cause of inadvertent unit 2 CVI signal of November 27, 1987, a unit 1 CVI signal was initiated while instrument mechanics were connecting test equipment to various electrical terminals associated with unit 2 radiation monitors. The work request had incorrectly specified a set of unit I terminals.

Since the unit 1 monitors were not in the block configuration, the CVI signal was initiated when the terminals were shorted together (reference' PRO 1-87-436).

3.

Received three additional inadvertent CVI signals from radiation monitors. Currently participating on special task force developed to investigate and resolve design problems with radiation monitoring system.

4.

Continued work to identify and resolve discrepancies with the TI-41 scaling and setpoint document. This work is in accordance with CAR 85-08-13 and is currently scheduled for completion by June 1, 1988.

5.

Centinued development and performance of procedures for various CSSC instruments that were previously not included in a periodic calibration program. This is in accordance with the corrective action for DQA Audit QSQ A-86-007-D01.

6 Completed corrective actions for CAQR SQP871430 concerning the installation and removal of Raychem splices in surveillance instructions.

7.

Completed corrective actions for CAQR SQP870546 concerning the compliance instrument requirements for 0-PI-14-198 and -268.

8.

Completed corrective actions for CAQR SQP870019 concerning the reliability of auxiliary feedwater flow instruments 1, 2-FM-3-142A.

9.

Completed corrective actions for CAQR SQN871350IDI concerning various ERCW system instruments not on the CSSC list.

_ -. -. - _ ~ -

'J.

s UNIT 1 1.

Prepared special maintenance instructions for replacement of the unit I containment sump Itvel transmitter in accordance with CAQR SQP870043.

The instructions are currently in the review cycle and field work will be scheduled when the procedures are approved and issued.

2.

Completed procedure revisions needed to ensure unit I technical specification instrument ranges (actual) agreed with the ranges specified in technical specifications. This was an NRC commitment item in accordance with CCTS NC0840208002.

UNIT 2 1.

Completed revision to SI-604 "Essential Instrumentation Operability Verification," to incorporate Phase I corrective action commitments to identify and verify proper configuration of sense line valves for various safety-related instruments (reference CCTS NC0870324029).

i s

IXSTMtXT roIXTENANCE nUHTMLY SunMRY 01-12-88 CDFP

".22,

U TL'XC SYS ADDRESS. DATE.,

DESCRIPTICN.

. CORRfCTIVE ACTIDH..

0116M4 1 LT 043 320 09/22/841-LT-048-320-F Ea10CFR50 kis3,RERACE ND FAILLRE FOUND; NOT MY E:ELLOWS CAMCC DAMGED SENSCR i:ELLCWS AND CHECK FILLED 02 TUBING OSSTRUCTION FOUND/REMDVED SYS CAPILLARY TU!:INC FER I.ELLOWt FROM CAPILLARY TUBING DH LPPER OBSTRUCTICN;PO!!ICLY UHERE WELDING ON TAP OF 1-LT-68-320. FOUND NO DBSTRUCTICH WP11907 DH M WR IB-120377, REPLACED BELLOWS MD FILLED PER IMI-118. REIMSTALLED SENSOR HOUSING MD TORGED 5-5-86. FINAL CALIBRATION,1E MINT., ! Pni UILL FE PERf 0RMED DURING RDUTIRE DiiTAGE PERf0RNANCE Or SI-94.1 0204470 2 In 070 0173 07/13/87 2-in-070-0173,EkHPRDM3,RIET.ON CM'LE THE MD5IFIER RIlt0H CABLE HAD SHCETE0 SHCRTED DUT. REPLACE WITH WEW CeltE CUT. THE MODULE WAS REPLACE 575 15887D01901 AND THE CALII<RATIDH VERIFIED ON SI-532.

0215!13 2 II 074 12 07/30/87 2-FI-07V12,EnXPRDaMALIlfATE fl0u THE IMDICATOR WAS FOUND DUT Of T0LERANCE INDICATCR 2-FIS-7412 TO PLUS OR MINUS HICH IN THE MID THROUGH HICH RANGE THIS 2Z FCR SI-118 MD SI-128.4.

COMDITIDH COULD HAVE CEEH CAUSED BY THE LIHES HEEDING BACKTILLIMG. Tile INDICATOR WAS CALIBRATED AND BACr. FILLED THEM RETURNED TO SERVICE.

2-FIS-074-0012-A HAS EEEN CHMGED IN THE FIELD FRL5 A C0FEINE INDICATCR AND SWITCHES TO SEPERATE INDICATOR MD FLDW SWITC115.

1:272'J4 : L3 003 0174 C4/22/37 2-LP,-00M174-0,E*MPRDm],0UTPUT FDUND TO THE MODITIER WAS TOUND TO HAVE A CAD LE UNSie!LE CH SI 75 PRINTED CIRCUIT I,HD/TC PRINTED CIRCUIT BOARD Whi REPLACED 575 8508-7009455. PER/CRMED CALIERATION FER SI-75. THE MDDIFIER WAS LEri IN TOLERMCE MD OPERASLE.

I;2: N 1 1 LT 003 0097 04/10/871-LT-003-0)i7-G,Eul0CTR50.49s,uNPRDd),1-IT WAS FOUND THAT THE LEVEL TRAN5MITTER LI-3-97 IS CRITTING NICH WEEDED IACKFILLING 1-LT-003-0097-G/THE LEVEL TRM!nITTER 1-LT-003~0097 G WAS CACKFILLED AND :'ETURHED TD SERVICE THEN THE LEVEL INDICATCR EAS VERITIED WITH OPERATICX3.

!?90003 2 F" 045 C030 C3/05/87 2-PDn-065-0080-A,ErKFF*n),FLPAIR (JO THE MUDIFIER MS FOUND TD EE DUT Cf CALIIRATE AS HICESSARY TOLERMCE L0u IN THE MID MD HIGH PANGES/THE MODIFIER WAS CALIBR ATED MD CuffLETED SECTIO 3 5.4 Of $1-188.2 F29S91 : I ?i7 013510/15/871-fi-067 01?6,CnNPRDs),THE INDICATCR THE TRMinITTER WAS FDL'hD TO FE D' T CF J

a l

i IN$lidnoti MINTEMNCE MONil!LY $thiARY 01-12-68 i

COMP nR2.... U iWC SYS ADDRESS. DATE... DESCRIPi!CN.

CO EECTIVE ACTIN..........

SHOWS APPROXIMIELY 2000 GPM WITH THE 10LERt.HCE HIGH TMlWCHWT TE ENTIRE HTX It1ATED RANCE EAU 3ING I E INDICATM TO HAYE A INCOR KCi K ADING. IE TRANSMITTER WAS ECALIleATED MD TE IN!!RUMDti LOOP KCECKED, THE LO(P HA3 IN TOLERMCE MD LUT A$ SUCH.

l

\\

MAINTENANCE

SUMMARY

(MECHANICAL)

i MECHANICAL MAINTENANCE MONTHLY REPORT FOR DECEMBER 1987 s

CONMON 1.

Completed repales on "B" auxiliary boiler.

2.

Completed repairs on traveling water screens.

3.

Continued repairs on control building roof.

4.

Completed repales on "B" CCS heat exch;nger.

UNIT 2 1.

Completed repairs on 2-FCV-70-1, -11, -197. -198, and -7258.

2.

Completed repairs on ESF coolers.

3.

Completed repales en A-train control room drive mechanism duct.

4.

Completed repales on 2-VLV-63-502, and -577.

5.

Completed repairs on refueling water purification pump.

6.

Completed repairs on condenser water boxes.

7.

Completed head replacement on "B" CCP oil cooler.

8.

Completed repairs on 2-FCV-62-86.

9.

Completed repairs on 2-LCV-37-1.

OTHER 1.

Continued efforts to reduce WR backlog.

2.

Continued efforts to close restart CAQRs.

3.

Continued efforts to close restart SALs.

4.

Continued review of Surveillance / Preventive Maintenance Instruction revisions.

5.

Continued efforts to close various workplans.

Y+'

. MECf.NICAL MINTENMCE MONTHLY

SUMMARY

01-12-88 CDNP PR2..

U MWC SY3 ADORE 31. DATE.... DESCRIPTION.

.............. CORRECTIVE ACTION.

0112195 2 !CV 047 0491D 10/15/87 2 FCV-c47 04910 A,[WPRDa],Ci2CK 10 SEE WATER LEMING THROUGH. Y E YE HAS WATER IF VRVE WILL SEAT OFF CGMPLETELY

. CUT IN TE YALVE I:DDY. LEAKAGE CAUSED I:Y EXCE!!IYE CCRR0! ION DilE TO WATER OUALITY/DISSEnBLED URIK, CLEANED AND INSTAltID EW SEAT AS3D%LYS AND PACKINC. REASSDSLED YALYE MD ETL' RED TO SERVICE. WRW-112195.

C222570 2 PCY 001 002312/04/97 2 PCV-001-0023-A,EnPRDahCM NOT A0JU$i $PRINC PLATE ItRDEN/REMIP)[0 DPERATOR VLU LIff CFF. AD1J!iMENT IS (CUND UP AND INTERNAL!. EPLACED SPRING ADJU$ TING ADfJSIDENT PLATE flISSING CUIK EM PLATE, CLEMED ALL PARTS, LUBRICATED AND REA!!D11tED DPERATOR., ElllRNED YALK TO SERYIEE, WRB 222570 1747418 2 VLU 042 0408 09/12/87 2-ULV C42-0608 3 PEff CRn APPRDPRIATE WORN PACKINC-EMOYED ALL Of THE OLD nAINTENMCE TO CCIRECT THE REASON FOR PACKING, CLEANED URVE STEM MD Stuffing CCECM IUILD UP ARD'.<D 5 TEM. RWP i'OX. REPACKED YALVE WITH EW PACKING AND J

RECUIRED.

RETURNED TO SERVICE.

[:251(40 2 P:!P 082 0002A2A 11/20/87 2 Pn.$-M2-)oC2A2A-A Pl#.P $ 50 TOR PJKD:C WDRM C(1PLING DUC TO AlWMM. CLIEKING F0l!E. COULD PE FAD HISEIGNMENT/ REPLACE COUN.ING MD CDUPL(ks.

PETURNED PUMP TO NORMAL. WRB-251040 M 5109 2 l'LV 043 053811/19/C7 2-ULV-048-0518-3,2-VLY-46 538 HA3 A NORMAL WEAR-REMOVED OLD FACKING MO PACKING LEAK; EXTEES$ OUILD UP OF IDRCN. IN!iALLED HEU PACKING KTURNED UALYE TO ARGUHD UALVE.

SERVICT..

E 15140 2 ICV 063 ella 11/09/87 2-FCV-C43 0110,Co.PRCn1PETCDCK DN AIR THE REGULATOR It i:AD/ REPLACED THE RECULATCR ! PIN! $0 WE CMNOT I:LEED RECUT.ATCR MD RETUENED 10 SERVICE PRE!!U2E Cff.

WRk-2r e )

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MICW.WirAL MIW1ENMCE !SillLY $UMARY 01-12-88 CCff PR2...

U FUNC SYS ADDRESS. DATE.,. DESCRIPTION......

.. CORRECTIYE ACTION..........

2.30513CFH KFEENCE LEM RATE.34 UALYE, CLEMED INTERES, REA$$EftLED 3Cfil.

VALVE MD ETURNED TO $CRUICE. 'THIS YALE IS BEING CHMCED Odi UNDER ENGINEERING CHANGE NOTICE 7061.

t245310 2 YLY 047 056?C OV23/87 2-YLY 047-054?C-A,EuMPRDu],2.YLV-47-542C DIRTY WATER, WIT MD SCALE. WRDNC FAILED 31-158.1 LEM RATE 30.329E SCFN. APPLICATION FOR VALYE/DISAISEMBLED GP REG.

VALYE, CLEMED INTERE!, EA3SD$ LED YALUE M ETURMFD TO $EkYJCE..THIS VALE It BEING CHMCED WI UNDER ENGINEERING CHANGE NOTICE 7099.

0245316 2 YLY 067 0542A OV23/87 2-RY-047-05428-A,CuMPRDu),2-YLY-47-542A DIRTY WATER, RU3T MD SCALE /DISA!!EMKED f AILED SI-158.1 LEM RATE 2.17 SETH VALYE, CLEMED INTERRt. REh!SOSLED YALVE AND RETURNED TO SERVICE. THIS UALYE It BEING CIMCED OUT UNDER

+

ENGINEERING CMME NOTICT 7081, ic245318 2 ULY 067 0575A OV29/87 2-ULV-067-0573h-A.EnNPRDE3,2-CV-47 575A VALVE LEAKING THRWGN. YEYE INTERMLS FAILED SI-158.1 LEM RATE k'EK DIRTY AND WSTED/DI!A!!EMKED YALVE, CLEMED INTERNALS MD SEATING

$ULTACE MD INITELID EN CASKET ON CONNET REA!!DBLED YALVE MD RETURNED TO 3ERVILE. WRB-245318 P245318 2 VLV 067 0575A OV29/87 2-YLY-047-0575A-A,EmMPRDR3,2 CV-67-575A VALVE LEAKING THROUCN. Y EYE INTER R $

FAILED SI-158.1 LEAE RAi[

WEPE CIRTY MD RUSTED /DI!A!!EMBLED YALVE, CLEMED INTERNALS MD SEATING

$UEFACE MD INSTELED NEW CASKET ON PONET KA!!DSLO YALVE AND RETURNED TO SEWItt, liRB-245318 f.2470701 'A V 070 064712/02/871-VLY-070-0647-A,ErMPRon],VALUE 13 VALVI HAD TRA$il AND LOO 1F SCALE LEMINC ThEOUCH HEEDED FDR NYDRO VDIT PARTICLES IN!!DE M ON CCHD PIPIhC KPAIR IN SUPPCRT OF L'R

!E AT./DISA!!DSLED YKYE, CLEANED YALVE B-234034.

SEATINC MD SEALING SURFACLS.

REA!300 LED YALVE MD RETUkNED TO

!E NICE. (WRB-247070) 1297733 2 ULU 070 0680 07/2d/87 2-VLV-070-0630-A.EtMPPDm3,THE YALVI IS PACKINC WDR Duis1tDtOVED VALYE PACKINC, LEMINC WATER OUT CF THE PACKING ! TEM CLEMED STUFFING BOX, REPACKED MD LEAK CFF LINE.

TICNTOED. RETURNED YALVE TO NORML SERVICE. (L'28-217733) i -

MECWif/4 MINTENANCE MONTRY SLtMRY 01-1248 Cat 1P nR2..,

U FUNC $13 ADDRE11. DATE... DESCRIPTION.,

CU RRECTIVE ACTIDM..................

[:114c,53 2 VLV 070 0687 04/C8/84 24V 070-0687-8,EnKPR00,24V-70-487 Ruti IN SYSTEM. POSSIItY DUE TO LOCAL TESTED TOGETHER W/2 TCN0 87 FAILED LEM RATE TESTINGS /DISAS!DiltID UALE 31 138.1 LEAK RATE T3T CLEMED INTERNAL 3, LAPPED SEAT AMD SIC.

REA!!ESLED VALVE MD REllDXD TD SERVICE. UlRB-114953)

]

0126373 2 FCV 070 008710/03/84 2-FCV-070-0037-B,EnNPR00,1XNER SEAL PACKING Is WDRN. INNER SEAL 13 tcLOW. SLIGHT LEAK DUT CT DUTER SEAL lt0WN./ REMOVED 01) PACKING AND REPLACED WITH NEW PACKING. REilENED YALVE TO NORMAL SEWVICE. (WRB-123373) 1130148 2 FCY 070 009010/03/86 2-fCV-070-0090-A,CnMPRDO, VALVE FAILED VALVE INTERNES DIRTY WITH RU$f

$I-158.1 (LLRT) REPAIR A5 KEEDED.

DEPD$111./ADJll3TED PACKING, DISASIEftLED VALVE MD REMOVED DISC. LAPPED DISC MD SCA13, CHECKED f!R CORRECT $[ATING.

CLEMED VALVE INTERNALS, REA31EMitED AND TORQllED. RETURNED VALVE 10 NORflAL SER 1202656 1 FMP 062 0230 09/10/841-pnp-062-0230-A,PunP $EAL 13 LEAKING WCRM MECHANICAL SEAL AND CREATIEG A rits PLEASE REPAIR AS 100N AS ETARIhst/ REMOVED PudP, REPLACED SEAlt, I,'DITIBLE lifRING3, 0-RING!, C ASKET!, DILER AND -

$HAff. INSULATED PunP MD ALIGNED PUMP.

0245;53 2 (CV 063 0023 08/31/87 2-FCV-043-0023-B,CnMPRDO,UALUE FAILED INTERK1! HAD A RU!T COLP,9CD TINT OM

$1-153.1 LEM RATE 1.4173 SCTH RETEQENCE PLliG ND SEAT /DISASTEnitED VALE LEAK RATE 0.145 $CfH.

REMOVED STEM MD PACKIEC. REATSD$ LED VALVE, Ih3TALLING FEW STEN. PLUG, SEAT, PIN CA;KEi! AND REPACKED VALVE.

INSPECTED STDI NUT, APPLIED LOCTITE AED STotED THL'EdD.

TN053 2 f CV 043 0023 08/31/87 2-FCV-063-0023-B,C9PRDO, VALVE FAILED INTERNAL $ HAD A P1f3T COLORLD TINT OM 1

!!-158.1 LEM RATE 1.4173 !CFH RETERENCE PLUG MD 3 EAT /DISA35EnnED VALE LEAK RATE 0.141 SCTH.

REr.0VED STER MD PACKING. REA!!D$ LED UALVE, INSTALLING HEW STEM, PLE $ EAT, PIN CASKETS MD RE/ACKED UN.VE.

INSPECTED SIEn HUT, APPLIED LOCTIIE M0 3TalaD TWEAD.

I N 3W 2 VLU O!?

05420 09/23/87 2-VLV-067-0562D-B,CuMPRDO VALVE DIRTY WATER, RUST MD i

2-67-562 D FAILED SI-158.1 LEAK RATE SCPLE /DISA!!DittED WALUE, CLEANED 3CTH REFEREFCE LEf.K RATE.36 tCFH. RWP INTERNALS, REA!!DSLED VALVE AND REGUIRED PETURNED 10 TERVICE. THIS VALUE 13 (EING CPt.NGED OUT UNDER ENCIKEERING CHA,9CE MOTICE 7099.

2245305 2 MV C67 05620 09/23/87 2-VLV-067-05628-B,E*HPPDO, VALVE DIRTY WATER, RUST AND SCALE. WRONC i

2-67-5620 FAILED SI 153.1 LEAK RATE APPLICATIDM FCR VALVE /DISASSEnttED l

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MAINTENANCE SUMMARi (MODIFICATIONS)

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SUMMARY

OF WORK COMPLETED MODIFICATIONS - CURRENT STATUS DECEMBER 1987 1

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Maior_ Capital Projects _:

PN7101: ECN 6388 - 500-kVA Switchyard Current Transformer Heaters Workplan (WP) 12223 is in progress pending safe access'to current transformers.

FN7102: ECN 5938 - Replace Feedwater Heaters 3 and 4 Preparation work is underway as time and manpower permits.

Installation of the monorail en unit 2 continues in preparation for the changeout of feedwater heaters 3 an8'A.

Structural steel reinforcement continues on unit I heaters 3 and 4.

This work will be moved out into FY 1986.

,PN7105: ECN 5009 - Essential Raw Cooling Water _(ERCW) Piping Changeout From Carbon Steel to Stainless Steel Some insulation activities remain incomplete and are being worked as resources permit. No additional pipe replacement is scheduled in the near future.

PN7108: ECN 6720 - Crane Consistency Program Unit 2 polar crane modification is complete..

Postmodification testing (PMT) by Electrical Maintenance is not complete. Unit 1 polar crane work started on July 6, 1987 and is approximately 90 percent complete. Auxiliary Building crane WP 12596 is in the approval cycle. Drawings have not been issued on the remaining cranes.

PN7115: ECN 6719 - Volumetric Intrusion Detection System ECN 6719 is still on hold. Security is dissatisfied with system operation. Security and DNE have not concluded discussions on resolution. Design is working on making the system functional.

PN7122: DCR_1373 Secondary Side Steam Generator Preservation ECN 5657 - Installation of Moisture Separator Reheater (MSR)

Drain Valves Work is essentially complete on all the ECNr. Some minor insulation installation activities are in progress as resources permit.

Maior_ Capital Projects (cont.):

ECN 5712 - Evacuation Alarms - Auxiliary Building WP 12663 All fieldwork complete.

ECN 5841 - Hot Shop Fire Protection / Evacuation Alarm -

WP 12664 All fieldwork for evacuation alarm complete. Awaiting Operations to get fans restarted so we can do functional test of firo protection.

PN7123: ECNs 5938, 6305. 6571 - Replace Foedwater Heaters 1 arid 2.

Units 1 and 2 and Eroded Pipe Modifications Group B is supporting PMT on heaters 1 and 2 on both units as requested. Insulation work on unit I continues.

1 PN7130: DCR 1156 - Post Accident Monitoring This work has slipped to allow work to continue oc priority unit 2 restart efforts. NRC commitment on NUREG 1.97 calls for unit 3 completion by September 1987 and unit 2 by U2C4.

A request has been sent to the NRC to move the unit I completion date to U2C4.

PN7132: DCR 2348 - Sewage Treatment Facility and Civil Upgrade New DCR for onsite sewage treatment facility upgrade. City of Soddy-Daisy will be responsible for interface work on site, lift station, and pipeline between Seguoyah Nuclear Plant and Highway 27.

PN7136: ECN 6259 - MSR Tube Bundle Replacement Complete except for PMT, inservice leak test, and final cleanup.

PN7152:,ECN 6808 - External Conduit Sealing Unit 2 work is complete.

Fieldwork is complete on unit I workplan.

_ Appendix R PN7159:

ECN 6300 - Additional Sprinklers and Draft Stops All work completed, t

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Major Capital Projects (cont e ECN 6300 - Sensors and Detectors All fieldwork and testing is complete.

PN7161:

FSN_5855 - Replacement of Doors A56 and A57 Installation of door A56 is complete, security of A56 to be worked later. Work on door A57 and interlocks will begin later.

PN7181: DCR 1898 - ECNs 6832 and 6596 - Dry Accive Waste (DAW)

Building Electrical interface work is complete.

PN7199: Miscellaneous Activities Under $100.000 This is for various work orders prepared for work under

$100,000 total site cost. This work is done as manpower resources are available that will not impact unit 2 restart effort.

Significant Items:

The following major significant items are under Operation and Maintenance Expense (0&M) and will continue to be until restart of unit 2.

1.

Fuse Program Work ECN 5880 - Work complete. Closeout in process.

ECN 6854 - The workplan is complete. Closeout in process.

3.

Cable Ampacity Program Unit 1 is in progress.

4.

Raychem Cable Splicing Work - Unit 2 Splice work complete - four functional tests remain which are l

held for outage by Operations.

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MajoL apital Erojects (cont.):

C 01h.e r_I tem.s ECN 5435 - Fire Doors The installation of weather stripping continues as resources permit.

ECN 5111 - Provide Permanent Power to Manholes 42-46 Electrical conduit and wiring inctallation for manholes 44-46 is complete according to WP 12262. Manholes 42 and 43 are being held for information from DNE on power cable routing ar.d terminations. FCR 4572R1 was sent to DNE and was logged in, but it was not sent to the responsible engineer. Manholes 42-46 will be worked by FCR 4572R1..

This. item is not considered unit 2 startup by DNE, and they will not authorize the engineer to do the necessary work to obtain pull cards or drawings for manholes 42-46.

FCR 4572R2 will be written to supersede 4572R1 for conduit and cable routing for manholes 42-46.

WP 17??6 is 100 percent complete. Workplan closure in process.

ECN 5503 - Evacuation Alarms O&PS WP 12482 is in work.

WP 12664 - Material arrived approximately November 28, 1987. Work is in progress and is approximately 50 percent complete. Additional material needs to be installed.

ECN 5599_ - Conduit Supports for Fif th Vital Battery and Wr ate Disposal Area WP 12186 was closed and sent to Drawing Control Unit (DCU) on November 27, 1987. All fieldwork is complete.

ECN 5609 - Air Compressors Makeup Water Treatment Plant Installation and checkout is complete. Work is complete. WP 11987 is fleid complete. Obtaining all documentation for closure of workplan.

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.ECN 5609 - Evacuation Alarm WP 12387 is in work and is 90 percent complete. Workplan change is needed to allow local testing of alarm horn.

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Major _ Cap _itsl Projects (cont.):

Othpr Items lcont.);

ECN 5626 - Containment Ladders, Unit 1 A workplan is being writton to incorporate this ECN. Modifications needs additional design information to complete. DNE needs to issue all drawings listed on this ECN. Work has not begun because of this holdup.

STI_ - 105 - The STI was written and approved to temporarily install Atwood monorail check valves in the vertical pipe run of ERCW to lower containment. Postmodification testing and final system restoration remains.

ECN 5726 - CAQR SQP870478 - Roroute Sense Line Piping for Train Separation to Panels 2-L-58 and 2-L-68 Fieldwork is complete.

In-service leak check will be performed during heatup.

,ECN_5 841 - Hot Shop Fire Detection WP 12360 is 95 percent complete. Material needs to be ordered and installed for PNL 0-L-633.

ECN 5935 - Correct Power Block Lighting Deficiencies WP 12437 has been approved and is in work. This is a nonrestart item. WP 12275 is being written, Modifications needs DNE to provide light mounting detail for Raw Watec Storage Tanks (RWSTs) and estimate design date after unit 2 restart. WP 5935-01 has been written to install security.

ECN 6005 - Replacement of AFW Air Ejector Tho workplan is complete except for the leak check to be done by SI-130.1 in mode 3.

ECN 6057 - Cable Tray Covers This activity is in progress for the unit 2 restart.

ECN 6082 - Vent for Boric Acid Tank (BAT)

Work has started.

ECN 6185 - Offsite Paging System Functional tests of the remote mobile units remain to be completed. _.

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Major Capital PrAjects (cont. ):

Other Items'(cont.):

ECN 619,6---Pressurizer Hangers and Valves PMT-is incomplete and scheduled for startup for. unit 1.

Remainlag unit ~? sock is scheduled for U2C3 refueling outage.

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ECN 6205 -. Replacement of Instrument Loop Power Supp1'y Fuses Unit 2 and unit 0 work-is complete except for spares. Bussman to furnish fuses January 4, 1988.

.ECN 6380 - Replacement of-Barton Pressure Transmitters-Fieldwork is complete.

Final closure awaiting-instruction revision by Instrument Maintenance.

ECN 6357 - Essential Raw Cooling Water (ERCW) Roof Access and Rails for Security Equipment-WP 12238 is boing held for'DNE approval of FCR showing installation details. No new date for release of approved FCRs or drawings by DNE has been established.

ECN,6388 Workplan I???3 - Craft support as needed for installation of hydrogen analyzers at 500-kV Switchyard (50 percent work complete).

ECNs 6402 (Unit 1) a'nd 6439 (Units 1 and 2) - Pressurizer Instrumentation Relocation Inservice tests will be performed when the system is brought up to temperature and pressure.

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.ECN_6437 - Replace FE-2-256 and 257 Unit 2 work is complete. Unit 1 lacks electrical work and calibration.

ECN 6455 - Upgrade CU-3 Box Battery Packs WP ]??95 has been issued. Modifications are complete for 121 of 129 CU-3 boxes. Work is presently in progress whenever manpower is available.

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ECNs 6491 and 6534 - Essential Raw Cooling Water {ERCW) Supports L

All restart work is complete. A workplan to remove previously installed piping was approved and will be worked as resources permit.

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Major Capital Projects (cont.):

Other Items (cont.):

dCN 6543 - Install Public Safety Access Portals and Modify Entrance Road Work is being held pending the release of drawings from DNE.

ECN 6557 - Installation of CO2 Abort Switches WP 12607 is 95 percent complete.

Functional tost completed obtaining documentation.

ECN 6601 - Removal of Unit 1 Emergency Gas Treatment System (EGTS)

Backdraf t Dampers PMT remains to be completed by the Mechanical Test Section. Fieldwork is complete.

ECN 6610 - Modify Air Return Fan Supports Unit I work is incomplete.

ECN'6631 - Modify Snubbers Documentation review is in progress for unit 2.

ECN 6689 - Relocation of Main Steam Power Operated Relief Valves (PORV)

Instruction revision was ipproved for unit 2.

Work on unit I has not started.

ECN 6698 - Repull 120-Volt Cables Unit 2 is complete. Unit 1 is 90 percent complete and held by ECN 6742.

.ECN 6706 14 Support Enhancement Repairs continue on unit 1 as resources allow.

Initial inspections for unit I lack approximately three supports for completion. Unit 1 evaluations are continuing. Documentation review of unit 2 work is in progress. This project is being combined with the calculation regeneration project for unit 1.

ECN 6715 - D/C Random Loads Complete.

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,Majo.c Capital Projects (cont.):

Other Items'(cont.):

- !q2i_6739 - Alternate Analysis Unit I work has been started.

ECN 6742 - Insta11' Fuses in Radiation Monitor Power Supply Circuits The workplan is complete for unit 2.

Unit 1 is 50 percent complete.

Instrument Maintenance cannot support until 1988.

ECN 6761 - East Valve Room (EVR) Blowout Panels Implementation of unit I work is progressing as resources are.

available. Work on a unit'2 EVR door was complete. However, a material change was requested by DNE'and is in progress.

ECN 6784 - Documentation to Show Pipe Class Broaks Workplan was approved.

,ECN 6808 Conduit External Sealing WP 12363 is field-complete.

ECN 6810 - Rework Category "C" Devices 1 Complete.

ECN 6815 - Installation Power Circuit Breaker Install 500-kV power circuit breaker and associated equipment for bay 1._ Retire 161-kV PCB and associated equipment. 'A total of eight workplsns will be required. Foundations and conduit are presently being. installed by WP 12654. WP 12740 for lighting, drain pipe, a'nd surface ground mat has completed the review cycle. WP 12739 for the structural steel installation has been written and is in the approval cycle. Completion of WP 12654 will probably be delayed somewhat by late delivery of anchor bolts.

ECN 6866 - Modification of Valve Room Doors Fieldwork is complete. However, DNE requested a material change which is in progress.

,ECN 6871 - External Conduit Soaling DGB/CB/ERCW Physical work is complete. Paperwork Jacks completion.

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e Major, Capital' Projects (cont.):

Other Items _(cont.1

'ECN'7000

' Addition of Support to Main Steam Dump Header Fieldwork is_ complete except for final inspections during heatup.

ECN 7078 - Install llangers - Main Steam Piping Complete except for final inspections during heatup.

ECM 7110 - Relocate Auxiliary Feodwater Controllers Work is complete.

ECN 7190 - Replace Duct Detectors and Install Thermal Detectors.

WP 7190-01 approved and in-work.

ECN 7294 - ERCW Check Valves for Turbine Building Compressors Fieldwork was started.

ECN 7297 - Auxiliary Air Compressor ERCW Relief Valves Fieldwork is complete. Instruction revision is in progress.

ECN 7322 - Thermal Interferences The workplan was approved and work completed.

DCN X00006A - Remove Hydrogen. Analyzers Tubing The workplan lacks PMTs (SI-219).

DCN 200018B - Install Needle Valve for Hydrogen Analyzers The workplan lacks PMTs (SI-219).

DCN_49 - Computer Room Air Conditioner The workplan is complete. Flow balancing is in progress.

DCN 70 - Hydrogen Analyzer Check Valves Workplan was completed, DCN 80/82_ - Flood Mode Spool Pieces j

The workplan lacks final paint cures.

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Major Capital Projects (cont.):

Other Items (cont.):

DCN 85/86 - Replace Penetration Room Dampers The DCNs were received, and the workplans were completed. PMT is in progress.

DCN 87 - AIW Silicon Rubber Cable Replacement Complete.

DCN 89 - Crane Wall Penetration A DCN was received, and the workplan was completed.

DCN 100 - Replace Valve 70-692 A DCN was received, and the workplan was written and placed in the approval cycle. An FCR was written to place a check valve in the 45 degree angle.

DCN 00068A - DCR 2259 - WP 12700 -Reassign power supply breakers for boric acid evaporator "A" and control rod drive. Work is complete, and the workplan is in hold for completion of work on ECN 5057.

DCN X00091C - Modify spreading room supply ductwork. Work is being held for Mechanical Engineering Branch to perform SI-244.2.

ECN 6429 - Component Cooling Heat Exchanger B Replacement DNE to procure piping, hanger, and PHE frame material. DNE to issue hanger drawings. Workplans are in work to fabricate and weld piping and fabricate and install new plate heat exchanger.

A DCN was recolved, and a workplan was written and placed in the approval cycle.

ECN 6860 - Control Room Bullet Resistivity - DCR 2268 - ECN 6860 WPs 12602, 12603, 12604, and 12605 are in work. Need modified lock sets for doors C-37, C-53, and C-60 returned from Overly Manufacturing Company.

ECN 7268 - Diesel Generator Remote Control Circuit Fuse Coordination l

Unit 1 WP 12653 is field complete and entering closure cycle.

(Presently having Surveillance Operating Instructions ISOIs) updated.)

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' >o Major _ Capital Projects (cont'.):

Other Items (cont.):

ECN 7269 - Diesel Generator Remote Control Circuit Fuse Coordination-Unit 2 WP 12653 is field complete and entering closure cycle.

(Presently

'having S0Is updated.)

ECN 7291/7292'- DCR 2259 - WP 12715 - Unit 1 ERCW Strainers and Unit 2' ERCV Strainers ECNs revised wiring and associated instrumentation to allow manual backwash and flushout of ERCW strainers.

Workplan is in work and approximately 75 percent complete.

Startup Activities List (SAL)

SAL Closure -~Many man-hours were spent closing these items.

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Appendix A - Internal Conduit Sealing Fieldwork is complete on WP 12272.

Instrumentation Verification Program There have been 953 discrepancies issued to MODS to date with 476 not required for restart. All discrepancies required for restart have been completed; 152 nonrestart discrepancies are open.

DCN 48 - Fieldwork is complete.

DCN 7A - Fleidwork is complete.

DCN 9_A

- Fieldwork is complete.

ECN 7297_ - Auxiliary Air Compressor - ERCW Relief Valves Complete.

DCN 14A - Fieldwork is complete.

DCN 36A - Fieldwork is complete.

ECN 7171 - Fieldwork is complete.

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Major Capital Projects (Cont.):

Other Items (cont.):

Lost Hanger Calculations ECNs 7276, 7282, 7283, 7284, 7290, 7293,-7295, 7296, 7298, 7299, 7300, 7302, 7303, 7304, 7305, 7307, 7308, 7312, 7313, 7320, 7321,.7325.and 25 WRs.

All currently identified restart work is complete.

Dry Active Waste Building ECN 6832 - WP 12473 - Complete.

WP 12449 - Requires energization of charged HVAC system for closure by Electrical Maintenance.

WP 12477 - Requires Instrument Maintenance calibration and checkout of area radiation monitor and air compressor.

WP 12478 - Complete.

WP 12612 - Complete. Closure ir process.

ECN 6596 - WP 12402 - Complete with the exception of 5 percent of paving to be completed spring 1988.

WP 12377 - Complete.

ECN 7268 - Diesel Generator Remote Control Circuit Fuse Coordination Unit 1 WP 12653 is field complete and entering closure cycle.

SOIs are being updated.

ECN 7269 - Diesel Generator Remote Control Circuit Fuse Coordination i

Unit 2 l

WP 12653 is field complete and enterir.g closure cycle.

l SOIs are being updated.

l DCN 00068A - DCR 2259/WP 12700 - Reassign Power Supply Breakers For Boric Acid Evaporator "A" and Control Rod Drive l

Work is complete. The workplan is on hold for completion of work on ECN 5057. i

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l M_alor, Capital Projects (Cont.):'

Other Items (cont.):

ECNs-7291/7292 - DCR 2259/WP 12715 - Unit 1 ERCW Strainers and Unit 2 ERCW Strainers ECNs revised wiring and associated instrumentation to allow manual backwash and flushout of ERCW strainers.

Workplan is in work and approximately 75 percent complete.

ECN 5712 - Evacuation Alarms Auxiliary Building WP 12663 - All fieldwork complete.

ECN 5503 - Evacuation Alarms O&PS WP 12664 - Material arrived approximately November 28, 1987.

WP is in work and approximately 50 percent complete.

ECN 5841 - Hot Shop Fire Protection / Evacuation Alarm WP 12637 - All fieldwork for evacuation alarm is complete.

Modifications is awaiting Operations to get fans restarted to complete functional test on fire protection.

ECN 7190 - Replace Duet Detectors and Install Thermal Detectors WP 7190-01 has been written and is in the approval cycle.

ECN 6388 - WP 12223 - Craft support as needed for installation of hydrogen analyzers at 500-kV switchyard. Work is 50 percent complete.

ECN 5111 - WP 12276 - Work is complete. WP closure is in process.

DCN X00059B - WP 12713 - Work is complete. WP closed.

DCN X00061A - WP 12678 - Work is complete. WP closed.

DCN X00078C - WP 12725 - Work is complete. WP closed.

DCR 2355 - ERCW - IDI:

DCN X00107A - WP 107 WP approval in process.

DCN X00108A - WP 108 WP approval in process.

ECN 5048 - WP 5048 WP approval in process..

o Major Capital Projects (Cont.):

Other Items (cont.):

ECN 5412 - WP 5412 WP approval in process.

ECN 5754 - WP 5754 WP approval in process.

ECN 6162 - WP 6162 WP approval in process.

ECN 5609 - Construct An Additional Makeup Water Treatment Plant WP 12576 - Work is in process and approximately 75 percent complete.

WP 12633 - Work is in process and approximately 50 percent complete. WP is being held for material ~on WP 12665-(Mechanical).

I WP 12731 - WP is approved and being held for material PR 74262A/74321A.

WP 12684 - WP is being held for material on WP 12682 1

(Mechanical), also awaiting instrumentation on PR.74233A.

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v?FSITE DOSE CALCULATION MANUAL CHANGES

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OFFSITE DOSE CALCULATION MANUAL CHANGES REVISION NO. 15 i

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SEQUOYAH NUCLEAR PLANT OFFSITE. DOSE CALCULATION MANUAL EFFECTIVE PACE LISTING REVISION 15

'Page Revision TOC 1 through TOC 2 Revision 15 1

Revision 6 2

Revision 14.

3 Revision 12 4

Original-5 Revision 14 6

Revision 4 7'

Revision 8 8 through 9 Revision 5 10 Revision 14 10a Revision 15 11 Revision 13

'12 Revision 12 13 Revision 14 14 through 15 Revision 15 15a Revision 12 16-Revision 13-16a Revision 8 Table 1.1 (Page 1)

Revision 12 Table 1.1 (Page 2)

Revision 15 Table 1.2 (2 pages)

Original Table 1.3 (8 pages!

Revirion 4 Table 1.4 Revision 12 Table 1.4A (removed from document)

Revision 9 Table 1.5 Revision 12 Tables 1.6 at.d 1.I Revision 5 Table 1.8 (2 pages)

Original Figures 1.1 and 1.2 Original Figure 1.3 Revision 3 17 Original 18 Revision 15 19 Revision 15 20 Revision 6 21 through 23 Revision 15 24 through 25 Revision 10 26 through 29 Revision 8 l

Table 2.1 (3 pages)

Revision 7 l

Table 2.2 Revision 5 Table 2.3 (3 pages)

Revision 10 Table 2.4 a-c Revision 5 30 Revision 13 30a Revision 15 l

Table 3.1-1 (5 pages)

Revision 13 Table 3.1-2 Revision 15 Table 3.1-3 Revision 13 Table 3.2-1 (3 pages)

Revision 13 Figure 3.1-1 ti rough 3.1-5 Revision 13 Figure 3.1-6 Revision 15 Figure 3.1-7 Revision 14 EPL-1 1

SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL DATES OF REVISIONS Original ODCM 02/29/80*

Revision 1 04/15/80**

Revision 2 10/07/80**

Revision 3 11/03/80, 02/10/81 04/08/81, 06/04/81**

Revision 4 11/22/82 (10/22/81, 11/28/81, 04/29/82**)

Revision 5 10/21/82**

Revision 6 01/20/83**

Revision 7 03/23/83**

Revision 8 12/16/83**

Revision 9 03/07/84**

Revision 10 04/24/84**

Revision 11 08/21/84**

Revision 12 02/19/85**

Revision 13 12/02/85 Revision 14 04/14/86 Revision 15 11/05/86***

!~

lY23 ff, RARC Charman IDstf s b

b 12f 7 Tb Manager, RC

'Date l

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• Low Power license for Sequoyah unit 1

• • RARC Meeting date

• • • Date approved by RARC Chairman Revision 15 l

EPL-2

-.-. ~,.

s I'.

For determining the beta dose to air:

DBn * 'm Kni DFSt (l'.17 ) '

i

-where:

D0

= beta dose to wir for sector n,' mrad.

n

'Xni

" air concent' ration of radionuclide i in sector n.pci/m3 DFDL = beta to air dose factor for radionuclide i, mead /yr per pCi/m3 t

= time period considered, ye m

The sector having the highest total dose.is then used to check compliance with specification 3.11.2.~2.

1.2.2 Todines and Particulates Step 1 Doses will~be calculated using the methodology described in this step.

If' 50 percent of the applicable limits are exceeded, step 2 will 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 s.i. tract from vegetable ingestion.

2.

Real cow locations are considered for the milk pathway and nearest resident-locations with home-use ssedens are considered for the vegetable pathway.

3.

The highest annual-average D/Q based on 1972-1975 meterolo61 cal data for ground level releases will be used for ingestion pathway doses.

4.

No credit is taken for radioactive decay.

5.

Releases of I-131 and I-133 are considered for the milk pathway.

Se-89, 15 Sr-90, Cs-134, and Cs-137 releases are considered for the vegetable pathway to the child bone. Co-58 and Co-60 releases are considered for the vegetable pathway to the teen g.i. tract.

6.

The calculations extrapolate doses assuming that only 90 percent of the total dose was contributed.

7.

The cow is assumed to grazo on pasture grass for the whole year.

R Revision 15

Equations For determining the thyroid dose f rom milk ingestion of 1-131 and I-133:

DTH =

x 10' (1.18)

(0.9) x 3.15 x 107 where:

DTH = thyroid dose from I-131 and I-133, mrem.

monthly release of nuclide i, Ci.

Qt

=

nuclide i milk ingestion dose factor to infant. (Table 1.7)

DF

=

D/Q = relative deposition rate, 2.96 x 10-'m-a, 0.9 = f raction of dose expected to be contributed by I-131 and I-133 3.15 x 107 s/yr.

=

10' = pCi/Ci 1

Equation 1.18 then reduces to:

DTH = 1.04x10-20 E Qi DFt i

For determining the bone dose from vegetable ingestion:

QtDFt D/Q 106 (1,19)

DBC =

t 7

3.15 x 10 (0.9) whoro:

15 DBC1 = bone dose to child from nuclide i, mrem.

Qt = monthly release of nuclide i, Cl.

f DFt = Vegetable ingestion dose factor to child, 2.25 x 1011, 1.36 x 1013, 1.59 x 1011, and 2.58 x 1011 2

mrem /yr per pCi/m -s for Sc-89, Sr-90, Cs-134, and Cs-137, respectively.

(As per Regule ery Guide 1.109 and NUREC/CR-1004 v

methodologies).

D/Q = relative deposition rate, 7.10x10-9s2 3.15x107 s/yr.

=

10' =

pCi/Cl.

0.9 = fraction of total bone dose expected to be contributed by Sr-90.

l Equation 1.19 then reduces to i

l DBC = 2.50 x 10-10 E Qt DFi l

i 15 Revision 15

For determining the gartrointestinal (g.i.) t ract dose from vegetable ingestion:

DGl.p = f(Q DF ) D/Q 10 6 g

j (1.20)

(0.9) 3.15 x 10' Where:

DGI = teen g.i. tract dose f rom Co-58 and Co-60, mrem T

Qg = monthly release of nuclide i, Ci DF. = Vegetable ingestion dose factor for the teen g.i.

tract, 3.87 x 109 2

mrem /yr per pCi/m -s for Co-58 and 3.31 x 1010 mrem /yr per pCi/m2 s for Co-60.

(Regulatory Guide 1.109 and NUREG/CR-1004 methodologies.)

12 D/Q = relative deposition rate, 7.10 x 10~9 m"2 7

't.I5 x 10 = s/yr IOC = pCi/Ci 0.9 = f raction of total g. i. tract dose expected to be contributed by Co-58 and Co-60 F.quation 1.20 then reduces to DGI7 = 2.50 x 10 f(QDF)

~10 g

Revision 12

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C TABLE 1.5 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES DFBI DF 2 DFS1 DF 2 7

g Kr-85m 1.17(+3)3 1.21(+3) 1.46(+3) 3.86(+3)

Kr-85 1.61(+1) 1.69(+1) 1.34(+3) 3.83(+3)

Kr-87 5.92(+3) 6.05(+3) 9.73(+3) 2.01(+4)

Kr-88 1.47(+4) 1.50(+4) 2.37(+3) 5.72(+3)

Kr-88+D 2.02(+4) 3.72(+4)

Kr-89 1.66(+4) 1.59(+4) 1.01(+4) 1.88(+4)

Xe-131m 9.15(+1) 1.53(+2) 4.76(+2) 2.18(+3)

Xe-133m 2.51(+2) 3.17(+2) 9.94(+2) 2.90(+3)

Xe-133 2.94(+2) 3.46(+2) 3.06(+2) 2.06(+3)

Xe-135m 3.12(+3) 3.30(+3) 7.11(+2) 1.45(+3)

Xe-135 1.81(+3) 1.88(+3) 1.86(+3) 4.84(+3)

Xe-137 1.42(+3) 1.48(+3) 1.22(+4) 2.50(+4)

Xe-138 8.83(+3) 9.00(+3) 4.13(+3) 9.25(+3)

Xe-138+0 2.65(+4) 2,81(+4)

Ar-41 8.84(+3) 9.76(+3) 2.69(+3) 5.54(+3) 1.

mrem /yr per pCi/m3 2.

mrad /yr per pCi/m3 3.

1.17(+3) = 1.17 x 103 Revision 12

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TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant P. O.

Box 2000 Soddy-Daisy, Tennessee 37379 January 13, 1988 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:

SEQUOYAH NUCLEAR PLANT - MONTHLY OPERATING REPORT - DECEMBER 1987 Enclosed is the Deccaber 1987 Monthly Operating Report to NRC for Sequoyah Nuclear Plant.

Very truly yours, TENNESSEE VALLEY AUTHORITY f/

(f,/./,

=

S.',J(. ' 51p h ^'

Pl' ant Manager Ecclosure cc (Enclosure):

Director, Region II Nuclear Regulatory Commission Office of Inspection and Enforcement Suite 3100 101 }brietta Screet Atlanta, Georgia 30323 (1 copy) pirector. Office of Inspection

's _

s and Enforcement Nuclear Regulatory Commission Washington, DC 20555 (10 copics)

Mr. T. Marston Electric Power Research Institute P. O. Box 10412 Palo Alto, California 94304 (1 copy)

INPO Records Center Suite 1500 1100 circle 75 Parkway j

Atlanta, Georgia 30339 (1 copy)

Mr. K. M. Jenison, Resident NRC Inspector

\\\\

O&PS-2, Sequoyah Nuclear Plant An Equal Opportunity Employer J